ML20211J326
| ML20211J326 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 10/30/1986 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| CON-#486-1423, REF-PT21-87-020-000 OL, PT21-87-020-000, PT21-87-20, NUDOCS 8611110105 | |
| Download: ML20211J326 (3) | |
Text
.
e ,. . ,
/ am.AIED gDHRESPONDENCR PHILADELPHIA ELECTRIC COMPANY garg 2301 MARKET STREET P.O. BOX 8699
'86 NOV -7 Pl2 :47 PHILADELPHIA. PA.19101 (zi s) a4 .sozo GFF IE 1- 81 iA:
" f,',, ,*,"," 00CKLTihu4 a m oc6... P oouer.. October 30, 1986 BR E "
$6CCYN4C PRODUCTION OEPAnfMSMT Re: Docket No. 50-352rd '
Dr. Thomas E. Murley, Administrator Region I U. S. Nuclear Regulatory Commission 631 Park Avenue '
King of Prussia, PA 19406
Subject:
Limerick Generating Station Unit 1 Standby Gas Treatment System Electric Heater Controller 10 CFR Part 21 Report
Dear Dr. Murley:
In a letter dated August 11, 1986 to you from S. L.
Daltroff, Philadelphia Electric Company reported, in accordance with 10 CFR Section 21.21(b)(3), failures of terminal blocks on Solltech power controllers in the Standby Gas Treatment System (SGTS) for Limerick Generating Station Unit 1. This letter report contained an error in the.model number of the deficient controllers that were replaced and the incorrect model' numbers of the qualified replacement controllers.
The correct model number of the deficient controllers that were the subject of the Part 21 report is H3-480-30-4-20.
Item 2 of the letter report listed the model number as H3-480-30 (4-20mA), and item 6 listed the model number as K3-480-30-4-20.
Item 7 of the letter report described the corrective action taken to correct the deficient controllers, i.e., they were replaced. The model numbers of the new replacement controllers are KN-480-30-9000 for tha master controllers and KN-480-30-9200 for the slave controllers. These controller models are environmentally qualified, and are the models selected and installed. Due to a communications error during the review of b303
~ - . _. -
Dr. Thomas E. Murley Page 2 i
the draft of the letter report, the incorrect model numbers for the new replacement controllers were listed.
We regret any inconvenience or difficulties that this error may have caused.
3 '
ry truly yours, k_ -
1
/
cc: Director, Office of Inspection & Enforcement (3)
E. M. Kelly, LGS Senior Resident Site Inspector See Attached Service List i
l l
i J
o
,j i
'i 1
3 a-b 1
ll r
i t
1 -
i
I ~
I
?..
E l:
L cc: Troy B.. Conner, Jr., Esq.
Benjamin H. Vogler, Esq.
Mr. Frank R. Romano Mr. Robert L. Anthony Ms. Maureen Mulligan Charles W. Elliott, Esq.
Barry M. Hartman,'Esq.
Mr. Thomas Gerusky Director, Penna. Emergency Management Agency Angus Love, Esq. ,
David Wersan, Esq.
Robert J. Sugarman, Esq.
Kathryn S. Lewis, Esq.
Spence W. Perry, Esq.
Jay M. Gutierrez, Esq.
? Atomic Safety & Licensing Appeal Board, j Atomic Safety & Licensing Board Panel Docket & Service Section (3 Copies) l E. M. Kelly l Timothy R. S. Campbell I
b ll 1
ll
- l f
j July 23, 1986
) .
1 2
k
j, , .e. .. _ . . - -
- . u s . c a . . . . .. , . . , . ,
l LICENSEE EVENT REPORT (LER) EaY.' oui.Y "'*
- l
- * *c.6,,, .ns eacu, u. u,
- Limerick Generating Station - Unit 1 ..m.m
- vaa oisiototof3t512 1 to,j o ,4 1 ESF Actuation Due to Personnel Error
- .....n. '
u.. .. '
.. u .. n . ,, ......,u,,n6....
j ..=va .a, v.a. v.a. w. "g',U
7f,,,*"; . v. .av s.a. *** w, ' .a=u c.., u .i.
?
o tsin lo go , , i
~ -
1 l0 0l1 86 gl 6 0 l4 l 7 0 l0 1l 0 3l1 8l6 o isin t o io , i c .
.............,n.....u.........i,..,,ni,
,,,,,,,,, c
=.= ..
g g _
. nn.
.m
.m n = > .
=> .
n.n..
nai .
\
- n., 1,0 , C .. .nu.i .
u.n . .
, ,g g, l [MrdMsg gkg.6<.gvyf hj.f:fY2OJfkM.v;ss
, 3. .g.blM H.9 9 4.lGHadi M,.a.lG H.s e
- 6.u.na co.v.e, ... v. un n ,
.... n u, .. .u.
e.6A C .
Charles A. Mengers. Senior Engineer. Licensing Section
,u n . . ... . . .
2 ,1.g 5 84l3 i i i5111814 i
, . , , . 6 uu .ne. .u. . ,. . . . , n., (
. s.uu .nn. ~ ..s ";~,n's "Wy::t' QQQ: e un enn. e.a .., =gn's my,oy :p yQip;g
, , , , , , , WM , , ,, , , , MM 7.1. / ' ' ,e dg[js:[,y.
S
- I I f I I I I I I I I f 1 I 'wd '
l .u.,6.a..ervat .. ., i st. Cia . e.. a .v. Cat v.a.
g.'" .u...
+
O v.. er, n. ~ oar,en. sue.,us
,,..c,,......,.,n..
ea n, T "
l l l Abstract: 86-047
- On October 1, 1986 at approximately 1420 hours0.0164 days <br />0.394 hours <br />0.00235 weeks <br />5.4031e-4 months <br /> a Nuclear Steam i Supply Shutoff System isolacion occu red because of personnel j* error. . While performing a surveillance test on the Reactor Core j -Isolation Cooling (RCIC) equipment area temperature instruments,
) an I&C Technician directed another technician to attach the
$ instrument leads of a Digital Volt Meter (DVM) across the normal
! open contacts in the RCIC isolation logic circuit. Because switch contacts in series with these normal open contacts were not first opened (as is stipulated in the surveillance initial ,
conditions), the isolation circuit energized thru the DVM. After an investigation, including confirmation that the isolation signal was initiated by a Digital Volt Meter completing the circuit around the normally open contacts, the logic was reset and the surveillance successfully completed.
P
. @go @ ,
r 2.'--= A-1
~
~
l UCENSEE EVENT REPORT ILERJ TEXT CONTINUATION I i.
'" =
- m
- essas .. u, j Limerit.k Generating Station .... o u .-=f . .' n.,g 4 Unit 1 issim
' I ~
I ~
. _- _. ..c , , n e, I Unit Conditions Prior to the Event: .
Operational Mode 1 (Power)
Unit at 100% Power .
Description of the Event:
~
At approximately 1420 hours0.0164 days <br />0.394 hours <br />0.00235 weeks <br />5.4031e-4 months <br /> on October. 1, 1986, while performing the 31 day surveillance functional-test ST-2-049-614-1 on
- Division 3, Nuclear Steam Supply Shutoff System (NSSSS), Reactor Core Isolation Cooling (RCIC) system equipment area temperature instrumentation, an I&C Technician directed an assisting Technician to attach a DVM across relay ~ contacts without fully
, considering adherence to surveillance test procedure sequence which caused an inadvertent RCIC isolation.
The isolation signal for the RCIC inboard isolation valve was initiated when the leads of.a Digital Volt Meter (DVM) being used
- to test the status of relay contacts (which are normally open) were attached across the contacts. Because the temperature trip l test switch on panel 10C640 was not first placed-in the " Bypass"
', position, the circuit was energized at the contacts. Connecting
} the DVM completed the circuit and initiated the isolation signal.
The initial conditions of surveillance test ST-2-049-614-1, which
! was being performed, stipulate that switch B21B-SSC on panel
[ 10C640 be placed in the " Bypass" position prior to starting the F test. Three technicians, with one technician acting as " lead",
f worked together' to perform the test. Because the relay contacts i being tested were difficult to r'each due to the high elevation of
[ the relay, the third technician was enlisted to assist in the surveillance. Due to a lapse in communications, one of the l technicians attached the DVM leads across the relay contacts ,
being tested before the other technicians placed the switch in the " Bypass" position. The lead technician failed to be explicit as to when the DVM should be connected.
. The Division 3 logic was initiated in this case by energizing the
, RCIC equipment area high temperature automatic logic circuit.
After verifying that the isolation circuit was energized through
f The EIIS codes for this system are BN and JM.
4,,,
L .
- l. ,.
4.....
UCENSEE IVENT REPORT ILER) TEXT CONTINUATION m.
s.,nes.ea.as
((s
'"**=*"8 : , , _ , , , , ,
Limerick Generating Station .. wism.f. t, nog i
. Unit 1 e ls le je go l3 l Sg 2 8 l 6 -
ol4li _ ojo 0l3 or 0l4 p a r u, - . __ 2 - --
m , , ,, ,,
Consequences of the Event: -
1 ...
L "
- The consequences of the event were minimd1 and were without adverse effects. If a RCIC initiation signal had occurred during the period that the isolation was activated, the operator could have manually reset the RCIC initiation logic to allow the steam supply isolation valve to be reopened and the RCIC turbine to be
! started.
l
[ Cause of the Event:
l J CAUSE CODE: Personnel Error - E7
! The unplanned ESP actuation (NSSSS, Division 3, RCIC isolation 4 signal) was caused by personnel error (an I&C Technician) while performing a 31-day surveillance test. The test initial conditions which stipulate that the test switch is,to be placed in the " Bypass" position prior to beginning the test was not completed. Because it was difficult to reach the relay contacts ,
being tested due to their elevated location, three I&C -
Technicians worked together in. order to perform the surveillance.
Due to a lapse in communications between the technicians, the DVM was attached before the test switch was properly positioned which completed the circuit.
The cause was confirmed by repeating the sequence of events.
i Corrective Actions:
1 J
1 The system logic was manually reset and the surveillance test was successfully completed.
Action Taken to Prevent Recurrence: ,
The event was discussed at an "all hands" meeting. All plant I&C Technicians were reminded that whenever two or more technicians j perform a surveillance, the lead technician is responsible for p
4 A-3
[ .
l l ;,did== =
l u u. ... . -
i UCENSEE EVENT REPORT ILER) TEXT CONTINUATION meen.anui s.,en anim
- e ma' =m sesses a e, y..,,,,, .
Limerick Generating Station 's** h "!-'.':' t
- b 71.*.?-
l Unit 1 8 1 9 n ,, - . w .= , m., a n s is ls ls [o l3 l Sg 2 8 l 6,_ 0g4ei Og0 0l4 or i 0 g4 I .
establishing adequate communications between technicians to -
,l.
control the sequence of testing in accorda,nce with the procedure. --
.i L Further, the I&C Technicians responsible for the isolation were i counseled on the importance of adherence to pro'cedures and the
! importance of following procedure sequence.
+
l Previous Similar Occurrences:
There were no previous similar occurrences of this nature on the RCIC system. Earlier Licensee Event Reports were reported however, on the failure to follow surveillance procedure sequence in Licensee Event Reports85-040 and 86-023. Further, improper j use of test equipment was reported i,n Licensee Event Reports 85-
- 016 and 86-021.
J
}
e j- .
l 5
+
4 4
L Ie
/. o r, e e I
C
- one een. es g,4 1 .
r -
I i
cc: Troy B. Conner, Jr. , Esq.
Benjamin H. Vogler, Esq.
l Mr. Frank R. Romano j' Mr. Robert L. Anthony Ms. Maureen Mulligan l
Charles W. Elliott, Esq.
Barry M. Hartman, Esq.
Mr. Thomas Gerusky Director, Penna. Emergency Management Agency Angus Love, Esq.
David Wersan, Esq.
Robert J. Sugarman, Esq.
l- Kathryn S. Lewis, Esq.
Spence W. Perry, Esq.
Jay M. Gutierrez, Esq.
Atomic Safety 4 Licensing Appeal Board Atomic Safety 4 Licensing Board Panel Docket 6 Service Section E. M. Kelly Timothy R. S. Campbell 4
l ,
i k
i A
l s
- -, PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 l
12im e4i.4ooo October 31, 1986 Docket No. 50-352 l
Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
Licensee Event Report Limerick Generating Station - Unit 1
) .
This LER concerns an ESF actuation caused by a~ technician l failing to follow the surveillance test procedure while l performing the 31 day surveillance tests on the RCIC equipment
! crea temperature instrumentation.-
i l
Reference:
Docket No. 50-352 l Report Number: 86-047 p Revision Number: 00
, Event Date: October 1, 1986 l Report Date: October 31, 1986 j Facility: Limerick Generating Station
- P.O. Box A,.Sanatoga,.PA 19464 k '
l This LER is being submitted pursuant to the requirements of l 10 CFR 50.73 (a)(2)(iv).
l t
} V fy truly yours, i
(vadbel G. M. Leitch Superintendent Nuclear Generation Division cc: Dr. Thomas E. Murley, Administrator, Region I, USNRC S. M. Kelly, Senior Site Inspector See Service List i
l i
(
~
i
l EP-208, Rev. 6 Page 1 of 12 3862111370 mar /jmv i PHILADELPHIA ELECTRIC COMPANY hM h t
b LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-208 SECURITY TEAM 1.0 PARTICIPANTS 1.1 Security Team Leader shall assign group leaders, activate the groups, and coordinate the team's activities.
1.2 Access Control Group shall perform access control activities.
1.3 Accountability Group shall perform personnel accountability activities.
1.4 Security Personnel shall maintain plant security, issue emergen.cy dosimetry to offsite support personnel, and assist in the evacuation of personnel and personnel accountability.
2.0 ACTIONS - IMMEDIATE
.2.1 Security Team Leader shall:
2.1.1 Call or assign someone to call required Team members by using EP-278, Security Team Phone List. -
2.1.2 Assign Group Leaders from available security personnel to the following groups to perform the duties in Section 3.1 as required for the situation:
A. Access Control B. Accountability AT AN AL h $$ TION, THE SECURITY
' TURBINE ENCLOSURE GATEON$ .N69)p* hTgON l
SHOULD BE KEO. 6k 2.1.3 i
EmergencyOpera: tid [nsiFaqility(EOF)Ifinformedby is to be 4 activated, contact 4 He Access Control Group Leader
- O "'"fMif71917" Tis'5"'"'
\ go i
l pio ry.
l EP-208, Rev. 6 Page 1 of 12 MJR/jmv I 2.1.4 If assembly with accountability is announced, perform the~following steps:
A. . Ensure that the Access Control Group Leader assigns l construction security personnel at the Personnel Processing Center to assist in controlling personnel BCCess.
~
B. Ensure that Operations security personnel are stationed at the appropriate personnel exit areas of the protected area.
C. Activate the Accountability Group to perform personnel accountability checks in accordance with EP-110, Personnel Assembly and Accountability.
2.1.5 If informed by the Emergency Director that a site evacuation is going to be declared, perform the following:
1 A. Ensure that the Access Control Group Leader assigns construction security personnel to the appropriate site (owner controlled) access control points and selected offsite assembly area.
/ B. Ensure that the Access Control Group Leader assigns construction security personnel to the selected site (owner controlled area) access control points.
C. Activate the Accountability Group to perform personnel accountability checks in accordance with EP-110, Personnel Assembly and Accountability.
D. Immediately notify the Emergency Director when the Access Control Group is at the appropriate site
, (owner control area) access control points and operations security personnel are at the selected personnel exit areas of the protected area so that l the site evacuation can commence.
1 i
2.1.6 Advise the Emergency Director concerning the need l for support of off-site security agencies, if l necessary. y l 2.1.7 Coordinate the actions of off-site security agency personnel if their assistance is required.
l 2.1.8 Use checklists in Appendix EP-208-3 as necessary.
lO u_ _ _ ___
_, _ _ . _ ~ _ _ - - __ _ _ , . .__ _ ..
l EP-208, Rev. 6 Page 3 of 12 MJR/jmv 3.0 ACTIONS - FOLLOW-UP i 3.1 Security Team Leader shall:
1 3.1.1 ' Review the current status of the emergency.
l l- 3.1.2 Ensure that the necessary groups are staffed and performing the appropriate sections of this
. procedure. Augment groups as necessary, by using
- EP-278, Security Team Phone List.
- 3.1.3 Keep the Emergency Director updated on status of the i team's activities.
1 3.1.4 Periodically re-evaluate the security situation and make appropriate recommendations to the Emergency Director.
- l 3.1.5 Use checklists in appendix EP-208-3 as necessary.
3.1.6 Implement LGS Plant Protection Procedures as appropriate.
i
- , 3.2 Access Control Group shall:
i I THIS GROUP IS COMPRISED OF CONSTRUCTION SECURITY FORCE MEMBERS. THE CONSTRUCTION SECURITY SHIFT SUPERVISION IS THE APPROPRIATE CONTACT.
l ACCESS TO THE SITE FOR SUPPORT PERSONNEL WITHOUT
! LIMERICK SECURITY BADGES DURING AN ALERT, SITE i
f EMERGENCY AND GENERAL EMERGENCY MAY'ONLY BE AUTHORIZED BY THE FOLLOWING PERSONNEL:
l EMERGENCY DIRECTOR SECURITY TEAM LEADER SITE EMERGENCY COORDINATOR
~
I 3.2.1- Be activated when directed by the Security Team j Leader.
i <
l 3.2.2 Receive instructions via the best means available 4 (telephone, radio, etc.) and obtain traffic vests
! from the Security stocks.
f iO i
- --,.... ---, ,- ..__,...n.. . , . . _ _
l l EP-208, Rav. 6 !
Page 4 of 12 l MJR/jmv v \IQ ,j 3.2.3 Be dispatched to locations in appendix EP-208-1 to control access: as required.
. SECURITY PERSONNEL NEED NOT BE POSTED AT A GATE THAT WILL REMAIN LOCKED DURING AN EMERGENCY.
3.2.4 If the EOF is activated, be dispatched to the EOF to perform the actions in EP-203, Emergency Operations Facility (EOF) Activation.
3.2.5 During assembly with accountability: .
- a. Dispatch Access Control Group members to the Personnel Processing Center to control personnel
- access.
3.2.6 During a site evacuation:
- a. Control access and vehicle traffic by providing access control group personnel at locations required by Appendix EP-208-1, site access (owner controlled area) Point Staffing for Site Evacuations, as required.
- b. Immediately notify the Security Team Leader when 1 access control group personnel are stationed at the i required site (owner controlled) access control
! points so the site evacuation ~can begin.
i 3.3 Accountability Group shall:
1- 3.3.1 For Personnel Accountability Check without Site Evacuation:
i a. Perform a personnel accountability check as detailed in EP-110, Personnel Assembly and Accountability.
! 3.3.2 For Site Evacuation
- a. Report to the Administration Guard Station and "
i perform personnel accountability in accordance with EP-110, Personnel Assembly and Accountability. .
I
!O I
i 1.--____ _ _ _ _ . _ , _ . _ _ - . . _ . _ _ .
l
- l. EP-208, Rev. 6 Page 5 of 12 MJR/jmv l 3.4 Operations Security Personnel shall:
3.4.1 Maintain plant security in accordance with Plant
. Protection procedures, and as directed by the Security Team Leader.
3.4.2 In the event of an Assembly with Accountability and Site Evacuation, assist personnel in the evacuation of affected areas and the performance of personnel accountability in accordance with EP-110.
3.4.3 Issue emergency dosimetry as directed by the-Personnel Safety Team Leader for incoming personnel per PP-2, Emergency Admittance Procedure.
3.4.4 Tor assembly with accountability:
- a. Assist the Accountability Group with the evacuation of non-essential personnel from the Protected Area.
- b. Perform the instructions detailed'in EP-110, 1 Personnel Assembly and Accountability.
3.4.5 For Site Evacuation:
( ) a. Control access to the protected area by providing i operations security personnel at locations required l by Appendix EP-208-2, Protected Area Access Point Staffing for Site Evacuation, as required.
- b. Perform the instructions detailed in EP-110, Personnel Assembly and Accountability.
- c. Immediately notify the Security Team Leader when operations security. personnel are' positioned and ready at the protected area personnel exit points.
4.0 APPENDICES 4.1 Appendix EP-208-1 Site Access (Owner Controlled Area) Point Staffing for Site Evacuation.
4.2 Appendix EP-208-2 Protected Area Access Point Staffing for Site Evacuation i 4.3 Appendix EP-208-3 Security Team Leader checklists.
O
l EP-208, Rev. 6 Page 6 of 12 MJR/jmv 5.0 SUPPORTING INFORMATION
'a 5.1 Purpose The purpose of this procedure is to provide guidelines for the activation and conduct of operation for the Security Team.
5.2 Criteria for Use 5.2.1 This procedure shall be implemented whenever; 5.2.1.1 Personnel assembly is announced; 5.2.1.2 Alert or higher classification is declared; 5.2.1.3 Site Evacuation is declared; 5.2.1.4 The Emergency Director deems the team's activation and operations necessary.
5.3 Special Equipment l 5.3.1 Traffic. Vests - Access Control Group.
5.4 References 5.4.1 Limerick Generation Station Emergency Plan 5.4.2 Limerick Generating Station Security Plan and Procedures 5.4.3 EP-278 Security Team Phone List 5.4.4 EP-110 Personnel Assembly and Accountability 5.4.5 EP-203 Emergency Operations Facility (EOF)
Activation 5.4.6 PP-2 Emergency Admittance Procedure ,
O
l EP-208, Rev. 6 Page 7 of 12 MJR/jmv l
l APPENDIX EP-208-1 SITE ACCES5 (OWNER CONTROLLED AREA) CONTROL POINTS STAFFING FOR SITE EVACUATION l Posting As Required l Construction Main Access Gate (Gate 1) l Construction Back Access Gate l Construction Sub-Gate (Gate 2) l Sanatoga Road Access Gate (Gate 7)
I F
I l
O l
w --_ --_ _ ._- _ - __ _ _ _ _ _ _ -
l EP-208, Rev. 6 Page 8 of 12 MJR/jmv
)l APPENDIX EP-208-2 l PROTECTED AREA ACCESS CONTROL POINT STAFFING FOR SITE EVACUATION Posting As Required -
~
TSC Exit ADMIN Exit .
l Security Gate 269' Turbine Enclosure PAB #1 North Vehicle Gate PAB #2 Water Treatment Building PAB #3 Cooling Tower Gate.
PAB #4 South Vehicle Gate PAB #5 Maintenance Area Gate PAB #6 Off Loading Gate D
I
, l' L
O
l
.. l l EP-208, Rsv. 6 Page 9 of 12 MJR/jmv fr%)
l APPENDIX EP-208-3 SECURITY INFORMATION ONLY
~
Notice of Personnel Arrival DATE: TIME: .-
Time of Notice: Time of Arrival:
i
- 1. Names of Persons Social Security Number A. A..
B. B.
C. C.
D. D.
E. E.
F. F.
t 2. Where personnel are arriving from
- 3. Name of person individuals are to see ,
4- Escorted by:
r 5.- Security Clearance Basis if unescorted access granted NAME SSN COMMENT A.
B.
C.
~
- l EP-208, Rsv. 6 Page 10 of 12 MJR/jmv i
v
- l. APPENDIX EP-208-3 SECURITY INFORMATION ONLY Notice of Vehicle Arrival ,
DATE: TIME:
1.. Type of Vehicle
- 2. License Number
- 3. . Company Truck registation number
- 4. Name of Driver
- 5. ~ Helper (If any)
- 6. Expected arrival time
- 7. Actual arrival time
}
0 e
O
l EP-208, Rav. 6 Page 11 of 12 MJR/jmv
~
^
l APPENDIX EP-208-3 ~
SECURITY INFORMATION ONLY Injured Person History DATE: TIME:
- 1. Name of Person Injured
- 2. Social Security Number
- 3. Payroll Number
- 4. Home Address x Company Injured Person Employed by 5.
- 6. Contamination (If any)
. ( (~'
- 7. How did injury happen?
i
- 8. Where did accident happen? (Location)
Location of gate required for access to protected area i
- 9. Under what circumstances did accident happen?
- 10. Was ambulance called? (At what time?) ,
- 11. Time of ambulance arrival
- 12. Time of ambulance departure
() 13. Where was injured taken? (Hospital name)
--,-,-..,,--e
_, ,,,-,n.- - - - - - -- - - - .--, .--.--
. . , , , , . s l EP-208, Rev. 6 Page 12 of 12
, MJR/jmv 1
N 4
(p ', .
U'
~
l APPENDIX EP-208-3 SECUMITY Il3 FORMATION ONLY Notice of Release DATE: TIME:
4
- 1. Notice of Site Evacuation A. Ascertain from Dose Assessment Team Leader the plume direction .
a x i
~
\
B. Note the course of plume so that gates or posts in the
- / plume path can be evacuated.
4 e
i 1) Annunciate this information to Operation Security and Construction Security ,
l
\
- 2) Check w'ith Security Forces to'ymake sure that Security Force Members.are not in path, make sure all gates,
! posts in path are locked and secured.
E.
l I,
i
, s.. s s x
- 3) Ensure by checking with H.P. that the planned path taken by rover patrols does not take them through plume path, s
s l
i L
f' Pcg2 1 of 5 i 3862111360 Revision 62 09/23/86 l r LIMERICK GENERATING STATION EMERGENCY PLAN PROCEDURE INDEX
=============s================================================
DATE OF LAST PROCEDURE REV. DATE SIGNED PERIODIC NUMBER NO. TITLE BY SUPER. REVIEW
==================c===========================================
EP-101 4 Classification of 03/25/85 10/26/84 Emergencies EP-102 11 Unusual Event Response 07/28/86 10/26/84 EP-102 0 Unusual Event Response 07/28/86 07/28/86 (Appendix 1)
EP-103 14 Alert Response 07/28/86 10/26/84 EP-103 0 Alert Response 07/28/86 07/28/86 (Appendix 1)
EP-104 13 Site Emergency Responre ^ 07/28/86 10/26/84 EP-104 0 Site Emergency Response 07/28/86 07/28/86 (Appendix 1)
EP-105 13 General Emergency Response 07/28/86 10/26/84
( EP-105 (Appendix 1) 0 General Emergency Response 07/28/86 07/28/86 EP-106 4 Written Summary 04/01/85 10/26/84 Notification EP-110 6 Personnel Assembly and 03/14/85 10/26/84 Accountability EP-120 3 Site Emergency Coordinator 04/01/85 10/26/84 EP-201 5- Technical Support Center 02/10/86 03/29/85 (TSC) Activation EP-202 5 Operations Support Center 04/01/86 04/01/86 c (OSC) Activation EP-203 6 Emergency Operations 05/27/86 04/01/05 Facility (EOF) Activation l EP-208 6 Security Team 09/23/86 09/23/86 c
EP-210 5 Dose Assessment Team 05/12/86 10/26/84 EP-211 2 Field Survey Group _ n n 1 (3 h /85 10/26/84 EP-220 CANCELLED O . 3
^
j pv y y h D '* * ~
EP-221 CANCELLED mwn!
p., .. g ,
p' EP-222 EP-230 5 CANCELLED Chemistry Sampling and W v "
. I y. 9 O 10/26/84 Analysis Team ..
0116p/44/q5 QOl 3; 'h
. , Pago 2 of 5 l .. ~ Rsvision 62 7
09/23/86
() LIMERICK GENERATING STATION
. EMERGENCY PLAN PROCEDURE INDEX
=============L2===============================================
DATE OF LAST PROCEDURE REV. DATE SIGNED PERIODIC NUMBER NO. TITLE BY SUPER. REVIEW
==============================================================
EP-231 12 Operation of Post-Accident 06/24/86 10/26/84 Sampling Systems (PASS)
EP-232 CANCELLED EP-233 7 Retrieving and Changing 04/01/86 10/26/84 Sample Filters and Cartridges from the Containment Leak Detector During Emergencies EP-234 7 Obtaining Containment 04/01/86 10/26/84 Gas Samples from the Containment Leak Detector During Emergencies EP-235 6 Obtaining Reactor Water- 04/01/86 10/26/84 Samples from Sample Sinks Following Accident Conditions r(~)%
\_ EP-236 5 Obtaining Cooling Tower 03/14/85 10/26/84 Blowdown Line Water Samples Following Radioactive Liquid Release after Accident Conditions EP-237 8 Obtair.ing the Iodine / 04/01/86 10/26/84 Particulate and/or Gas l
Samples from the North l
Vent Wide Range Gas I
Monitor (WRGM)
EP-238 5 Obtaining Liquid Radwaste 04/01/86 10/26/84 Samples frc4n Radwaste Sample Sink Following Accident Conditions r.r - e. 4 v CANCELLED EP-241 10 Sample Preparation and 06/24/86 10/26/84 Handling of Highly Radioactive Liquid Samples EP-242 5 Sample Preparation and 03/28/85 10/26/84 Handling of Highly Radioactive Particulate Filters and Iodine Cartridges 7 Sample Preparation and 06/24/86 10/26/84 t()EP-243 _ __
Handling of Highly Radioactive Gas Samples
. Paga 3 of 5 l R2vicion 62 09/23/86 g (,-) LIMERICK GENERATING STATION EMERGENCY PLAN PROCEDURE INDEX
~
======================================================t=======
DATE OF LAST PROCEDURE REV. DATE SIGNED PERIODIC NUMBER NO. TITLE BY SUPER. REVIEW
==============================================================
EP-244 3 Offsite Analysis of High 03/12/85 10/26/84 Activity Samples EP-250 2 Personnel Safety Team 12/12/84 10/26/84 EP-251 3 Plant Survey Group 04/01/86 04/01/86 1
52-252 8 Search and Rescue /First Aid 09/02/86 07/31/86 Group EP-253 0 Personnel Dosimetry, 12/12/84 12/12/84 Bioassay, and Respiratory Protection Group EP-254 3 Vehicle and Evacuee Control 02/04/85 10/26/84 Group EP-255 2 Vehicle Decontamination 12/12/84 10/26/84 g_ EP-260 2 Fire and Damage 12/12/84 10/26/84 Control Team EP-261 2 Damage Repair Group 12/12/84 10/26/84 EP-272 CANCELLED EP-273 CANCELLED EP-275 CANCELLED EP-276 7 Fire and Damage 02/10/86 02/10/86 Team Phone List EP-277 9 Personnel Safety 05/12/86 01/09/86 Team Phone List EP-278 7 Security Team Phone List 05/12/86 02/10/86 EP-279 8 Emergency Operations 05/12/86 10/26/84 Facility (EOF) Group Phone List EP-280 9 Technical Support 05/12/86 02/10/86 Center Phone List EP-282 6 Government and- 02/10/86 04/22/85 Emergency Management Agencies Phone List
_. .2f~~~ 6 Company Consultants 05/12/86 02/10/86 and Contractors
_ Phone List
. Paga 4 of 5 l 4.' Revision 62 09/23/86
() LIMERICK GENERATING STATION EMERGENCY PLAN PROCEDURE INDEX
~
==============================================================
DATE OF LAST PROCEDURE REV. DATE SIGNED PERIODIC NUMBER NO. TITLE BY SUPER. REVIEW
==============================================================
EP-287 3 Nearby -Public and 02/11/85 10/26/84 Industrial Users of Downstream Water EP-291 8 Staffing Augmentation 09/02/86 09/02/86 EP-292 9 Chemistry Sampling and 12/18/85 04/22/85 Analysis Team Phone List EP-294 9 Dose Assessment Team 05/27/86 01/09/86 Phone List EP-301 1 Operating the Evacuation 12/12/84 10/26/84 Alarm and River Warning System EP-303 3 Local Evacuation 12/12/84 12/12/84
[ EP-304 3 Partial Plant Evacuation 12/12/84 10/26/84 ED-305 5 Site Evacuation 03/25/85 10/26/84 f EP-30o "i ~~tvacuation of the 02/10/86 10/26/84 Information Center EP-307 2 Reception and Orientation 12/12/84 10/26/84 I of Support Personnel EP-312 5 Radioactive Liquid 01/09/86 01/09/86 Release FP-111 2 Distribution of Thyroid 12/12/84 10/26/84 Blocking Tablets Ei 31' 1 Emergency Radiation 03/29/85 12/06/84 Exposure Guidelines and Controls Er-315 8 Calculation of Offsite Doses 09/02/86 01/09/86 During a Radiological Emergency Using RMMS in the Manual Mode RP-116 4 Cumulative Population and 02/10/86 02/10/86 Near Real-Time Emergency Dose Calculations for Airborne Releases Manual Method FD 217 5 Determination of Protective 09/02/86 07/15/86 Action Recommendations i
EP-318 2 Liquid Release Dose 04/01/85 04/01/85 Calculations Method for
() Drinking Water t
Pcga 5 of'5 l Revision 62 09/23/86 p( LIMERICK GENERATING STATION EMERGENCY PLAN PROCEDURE INDEX u=======================================================s=================
DATE OF LAST PROCEDURE REV. DATE SIGNED PERIODIC NUMBER NO. TITLE BY SUPER. REVIEW
========================================================================== ,
EP-319 2 Fish Ingestion Pathway Dose 03/29/85 '03/29/85 Calculatior.
EP-325 3 Use of Containment Dose 02/27/85 10/26/84 Rates to Estimate Release Source Term EP-330 4 Emergency Response Facility 03/14/85 10/26/84 Habitability EP-333 1 Adjustment of Wide Range Gas 05/08/85 05/08/85 Monitor Conversion Factors EP-401 3 Entry for Emergency Repair 04/01/86 04/01/86 -
and operations EP-410 3 Recovery Phase Implementation 03/29/85 10/26/84 EP-500 2 Review and Revision of 12/12/84 10/26/84 Emergency Plan
{
l O
\
- t. , l l
l l
i PHILADELPHIA ELECTRIC COMPANY !
2301 MARKET STREET . _ . . _ _ _ _ _ _ _ _ _ . _ _ _ _ - - - . __ .
P.O. BOX 8699 PHILADELPHIA PA.19101 SHIELDS L. DALTROFF
~" "
October 27, 1986 Re: Docket Nos. 50-352 50-353 Dr. Thomas E. Murley Region 1 Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Dr. Murley:
Enclosed are two copies of Limerick Generating Station Emergency Plan Implementing Procedure EP-208, Rev. 6. This procedure is submitted per regulations in 10 CFR 50, Appendix E, Section V.
Two copies have been sent under separate cover to the Document Control Desk.
Very truly yours,
- ~1
}
s/ - cdd 7 -
Enclosure cc: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 E. Kelly, Resident Site Inspector - LGS See Service List Attached
r .
1, e ** O C:
G.
L cc: Troy B. Conner, Jr. , Esq. (whenclosure)
J: Benjamin H. Vogler, Esq. (w/ enclosure) 1 Mr. Frank R. Romano (w/o enclosure)
- . Mr. Robert L. Anthony (w/o enclosure)
J. Ms. Maureen Mulligan (w/ enclosure)
~
Charles W. Elliott, Esq. (w/ enclosure) j Barry M. Hartman, Esq. (w/ enclosure)
- Mr. Thomas Gerusky (w/o enclosure) f' Director, Penna. Emergency (w/o enclosure) i Management Agency Angus Love, Esq. (w/o enclosure)
David Wersan, Esq. (w/o enclosure)
Robert J. Sugarman, Esq. (w/o enclosure) j Kathryn S. Lewis, Esq. (w/o enclosure)
- Spence W. Perry, Esq.. (w/o enclosure) j- Jay M. Gutierrez, Esq. (w/o enclosure)
Atomic Safety 6 Licensing Appeal Board (w/o enclosure) l (w/o enclosure)
Atomic Safety 4 Licensing Board Panel Docket 6 Service Section (w/ enclosure)
? E. M. Kelly (w/o enclosure)
- Timothy R. S. Campbell (w/o enclosure) l l
l i
{
i l
F I
I l
r
)
i l
t p
<