IR 05000322/1980001
| ML17150A142 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 04/14/1981 |
| From: | Brunner E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Pollock M LONG ISLAND LIGHTING CO. |
| Shared Package | |
| ML17150A143 | List: |
| References | |
| NUDOCS 8105070483 | |
| Download: ML17150A142 (31) | |
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PROCEDURE COVER SHEET PENNSYLVANIA POWER 8( LIGHT CO.
SUSqUEHANNA STEAM ELECTRIC STATION PERSONNEL ANO VEHICLE CONTAMINATION SURVEYS EP-IP-014'evision
Page 1 of 9 Effective Date Expiration Date
-
- 5" Revised Expiration Date
'0
Prepared by Reviewed by PORC Review Requi Approved by Ye (~
No (
Date tG Date Date Sec~i, n cad PORC Meeting Number Superintendent of Plant O~te Date
~'7 S~
FORM AO-gA-101-1, Rev.
Page 1 nf
D
EP-IP-014 Revision
Page 2 oi 9 SECTION 1.0 2.0 3.0 4.0 5.0 6.0 PURPOSE SCOPE REFERENCES RESPONSIBILITIES DEFINITIONS INSTRUCTIONS TABLE OF CONTENTS ATTACHMENTS PAGE r
ATTACHMENTS Action Step -
Emergency Dir'ector/
Radiation Protection Coordinator Action Step -
Emergency Radiation Monitor(s)
C Action Step Security Coordinator D
Action Step Administrative Coordinator/
Administrative Support Mgr PAGE
EP-IP-014 Revision
Page 3 of 9 1.0 PURPOSE The purpose of this procedure is to describe the control methods, locations and limits for Personnel and Vehicle Contamination Surveys.
Z.O SCOPE To provide methods of surveying and decontaminating personnel and vehicles during Emergency Conditions.
3.0 REFERENCES 3.1 HP-TP-624,
"Personnel Decontamination" l
3.2 HP-TP-270,
"Operation. of RM-14" 4. 0 RESPONSIBILITIES 4. 1 The EMERGENCY DIRECTOR/RADIATION PROTECTION COORDINATOR/RADIATION SUPPORT MANAGER is responsible for determining requirements for personnel and vehicle decontamination and for ensuring that sufficient personnel are made available to control and monitor-personnel and vehicles utilized during an Emergency Condition.
4.2 The SECURITY COORDINATOR is responsible for ensuring that vehicles and personnel leaving the site exit via contamination control points and offsite team vehicles and/or ambulance vehicles, requiring decontamination, have site access clearance.
4.3 The ADMINISTRATIVECOORDINATOR/ADMINISTRATIVESUPPORT MANAGER is responsible for ensuring provision for transportation of offsite team vehi cl e s, requiring deco ntami na iton, on s ite.
5. 0 DEFINITIONS 5.1 Lar e Area Smear (LAS) - The use of a maslin type cloth in swiping a
large surface sq. ft.).
This technique deviates from normal swiping techniques and provides a quick, conservative estimate of loose surface contamination.
5.2 Corrected Counts Per Minute (CCPM) - Net count rate in an RM-14/HP-210 or equivalent after subtraction of the background count rat EP" IP-014 Revision
Page 4 of 9 6.0 INSTRUCTIONS 6.1 Upon determination that Personnel and Vehicle Contamination Surveys are needed, the EMERGENCY DIRECTOR/RADIATION PROTECTION COORDINATOR/RADIATION SUPPORT MANAGER will follow the instructions in Attachment A, Action Step - EMERGENCY DIRECTOR/RADIATION PROTECTION COORDINATOR/RADIAITON SUPPORT MANAGER.
6.Z At the direction of the EMERGENCY DIRECTOR/RADIATION PROTECTION COORDINATOR/RADIATION SUPPORT MANAGER, the EMERGENCY RADIATION MUNITOR will follow the steps in Attachment B, Action Step -
EMERGENCY RADIATION MONITOR.
6. 3 At the direction of the EMERGENCY DIRECTOR/RADIATION PROTECTION COORDINATOR/RADIATION SUPPORT MANAGER, the SECURITY COORDINATOR will follow the steps in Attachment C, Action Step - SECURITY COORDINATOR.
6.4 At the direction of the RADIATION PROTECTION COORDINATOR/RADIATION SUPPORT MANAGER, the ADMINISTRATIVECOORDINATOR/ADMINISTRATIVESUPPORT MANAGER will follow the steps in Attachment D, Action Step-ADMINISTRATIVECOORDINATOR/ADMINISTRATIVESUPPORT MANAGE Attachment A
EP-IP-014 Revision
Page 5 of 9 A.1.0 ACTION STEP EMERGENCY DIRECTOR RADIATION PROTECTION COORDINATOR RADIATION SUPPORT MANAGER The EMERGENCY DIRECTOR/RADIATION PROTECTION COORDINATOR/RADIATION SUPPORT MANAGER will:
A.1.1 A.1.2 A.l.3 Insure EMERGENCY RADIATION MONITOR(s) are dispatched to contamination control point, Post 15 or 1,
EOF parking area or the hospital as appropriate.
If Post 15 or 1 are not available because of high radiation or contamination levels, dispatch MONITOR(s) to an area where Background levels are
< 300 cpm.
Determine if vehicles and/or personnel are contaminated and will require surveys or are free to egress SSES.
Page 1 of
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Attachment
EP-IP-0.14 Revision
Page 6 of 9 ACTION STEP EMERGENCY RADIATION MONITOR Check Mhen personnel contamination surveys are required during EMERGENCY CONDITIONS, the RADIATION MONITOR wi1l:
8.1.1 Ensure egressing persons pass through portal monitors at contamination control point if functioning or use RM-14/HP-210 or equivalent for whole body frisking.
8.1.2 8.1.3 Monitor offsite team members and/or emergency medical personnel using an RM-14/HP-210 or equi val ent for who 1 e body friski ng.
Personnel are considered contaminated if levels of
> 500 cpm above background are detected.
8. 1.4 If personnel are contaminated, insure the following steps are taken:
B. 1.4. 1 Oon protective clothing to contain contamination, if necessary.
8. 1.4.2 Direct contaminated persons to an appropriate facility to decontaminate as per HP-IP-624, Personnel Decontamination NOTE:
IF NASAL CONTAMINATION IS DETECTED, CONSIDER Internal Dosimetry Program 8.1.5 Complete Form HP-TP-624-1, Personnel Contamination Report, and transmit to TSC Radioman or EOF communicator.
8.2.0 Mhen vehicle contamination surveys are required during EMERGENCY CONDITIONS, the RADIATION MONITOR will:
8.2.1 If it is determined that vehicles may be contaminated:
8.1.2. 1 Take a
LAS and count it on an RM-14/HP-210 or equivalent.
Page 1 of 2
Attachment
Page 7 of 9 8 ~ 1.2 '
Vehicles are considered contaminated when levels of > 500 cpm above background are detected.
8.2.2 8.2.3 If offsite team vehicles and/or ambulance vehicles are contaminated, insure the following steps are performed when appropriate.
8.2.Z. 1 Perform whatever decontamination possible at location.
8.2.2.2 If further decontamination is required per 82. 1.2, direct the vehicles to be transported to the inspection pit onsite.
When contaminated vehicles are onsite, insure the following steps are performed when appropriate..
8.2.3.1 8.2.3.2 Insure inspection pit drains are plugged properly.
Position contaminated vehicles over the inspection pit and hose vehicles down.
NOTE:
LIQUID WASTE FROM CONTAMINATED VEHICLES WILL REMAIN IN THE INSPECTION PIT UNTIL IT IS SAMPLED, BATCHED AND RELEASED.
B.Z.3.3 Re-survey vehicles per 8.2. 1 8.2.3.4 Quarantine vehicles which cannot be decontaminated by hosing.
Page 2 of 2
f
Attachment C
EP-IP-014 Revision
Page 8 of 9 CHECK ACTION STEP SECURITY COORDINATOR The SECURITY COORDINATOR ail 1:
C.1.1 C.1.2 Direct personnel and vehicles to appropriate contamination control point.
Insure site access clearance for offsite team vehicles and/or ambulance vehicles requiring decontamination.
Page 1 of
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CHECK Attachment D
EP-IP-014 Revision
Page 9 of 9 ACTION STEP ADMINISTRATIVECOORDINATOR/ADMINISTRATIVESUPPORT MANAGER D.1.0 The ADMINISTRATIVE COORDINATOR/ADMINISTRATIVESUPPORT MANAGER wi 1 1:
D. 1. 1 Make provisions for the transportation of offsite vehicles from EOF parking lot on to the site for decontamination, if necessary.
Page 1 of
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PROCEDURE COVER SHEET PENNSYLVANIA POWER & LIGHT CO.
SUSQUEHANNA STEAM ELECTRIC STATION RECONSTRUCTION AND ACCIDENT CLOSE OUT EP-IP"038 Revision
Page 1. of 9 Effective Date,~
Expiration Date Revised Expiration Date Prepared by Reviewed by PORC Review Req Approved by S
d Y ()
No()
He Date
Date
,Date PORC Meeting Number 2-- o 0/
Superintendent of Plant Date S /0 Date 4-lO'-V~
FORM AD-QA"101"1, Rev.
Page 1 of
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Page 2 of 9 TABLE OF CONTENTS SECTION 1.0 2.0 3.0 4.0 5.0 6.0 PURPOSE SCOPE REFERENCES RESPONSIBILITIES DEFINITIONS INSTRUCTIONS PAGE.
ATTACHMENT ATTACHMENTS PAGE A
In-Plant Radiological Considerations
Off-Site Radiological Considerations
EP-IP-038 Revi sion
Page 3 of 9 1.0 PURPOSE The purpose of this procedure is to:
1.. 1.
Reconstruct the event sequences associated with the cause and control of the emergency.
1.2.
Reconstruct the radiological conditions which existed during the emergency.
1.3 Assess the radiological consequences
.of the emergency.
2.0 SCOPE Provide a. list of items to be considered when reconstructing and assessing the emergency.
3.0 REFERENCES 3. 1 NUREG 0654, Planning Standards and Evaluation Criteria 3.2.
NUREG 0696, Functional Criteria for Emergency Response Facilities 3.3 NUREG - 0731, Guidelines for Utility Management Structure and Technical Resources, September 1980 3.4 SSES Emergency Plan 4. 0 RESPONS I8ILITIES 4. 1 It is the responsibility of the SUPERINTENDENT OF PLANT to reconstruct the sequence of events associated with the emergency, assess the adequacy of responses and document the lessons learned of any EMERGENCY which did not result in activation of the EOF.
4.2 It is the responsibility of the MANAGER-NUCLEAR SAFETY ASSESSMENT GROUP to reconstruct the sequence of events associated with the emergency, assess the adequacy of the responses and document the lessons learned of any EMERGENCY which did not result in activation of the EOF.
4.3 It is the responsibility of the RADIATION PROTECTION COORDINATOR to reconstruct the on-site radiological conditions associated with the
'emergency and assess doses to in-plant personnel.
In the event the EOF was not activated, the RADIATION PROTECTION COORDINATOR is responsible to reconstruct the off-site radiological conditions and assess doses to the public and other off-site personne EP-IP-038 Revision
Page 4 of 9 4.4 It is the responsibility of the RADIATION SUPPORT MANAGER to reconstruct the off-site radiation conditions and assess doses to the public and other off-site personel in the event the EOF was activated 4.5 It, is the responsibility of the RADIOLOGICALAND ENVIRONMENTALSERVICES SUPERVISOR to review and approve all radiological reports resulting from activities outTined in this procedure; 4.6 It is the, responsibility of the VICE PRESIDENT-NUCLEAR OPERATIONS to review and approve. all reports resulting from activities outlined in this procedure and implement a fol'low-up corrective action program, as appropriate.
5.0 DEFINITIONS 5.1 EREMP Emergency Radiological Environmental Monitoring Program 5. 2 REMP Radiological Environmental Monitoring Program 5.3 TLD - Thermoluminescence Dosimeter 6. 0 INSTRUCTIONS 6.1 If the EOF was not activated, the SUPERINTENDENT OF PLANT will issue a.
report including:
6. 1.1 Reconstruction of the sequence of events associated with the emergency (timeline and detailed supporting documentation packages).
6. 1.2 Determination of the cause of the emergency.
6. 1.3 Assessment of the extent of damage sustained by the plant.
6. 1.4 Assessment of the adequacy of response.
6. 1.5 Identification of lessons learned.
6.2 If the EOF was activated, the MANAGER NUCLEAR SAFETY ASSESSMENT GROUP will issue a report. including:
6.2.1 6.2.2 Reconstruction of the sequences of events associated with the emergency (timeline and detailed supporting documentation packages).
Determination of the cause of the emergenc EP-IP-038 Revi sion
Page 5 of 9 6.2,.3 Assessment of the extent of damage sustained by the plant.
6.2..4 Assessment of the adequacy of response.
6'.2.5 Identi-fication of lessons learned.
6.3 RADIATION PROTECTION COORDINATOR Duties 6.3.1 The RADIATION PROTECTION COORDINATOR will issue a report, uti'lizing the guidance in Attachment A, which addresses:
I 6.3.1.1 Character'ization of in-plant radiological conditions, 6.3. 1.2 Personnel exposures.
6'.3. 1.3 Characterization of radiological conditions in restricted. area..
6.3.2 If the EOF was not activated, the RADIATION PROTECTION COORDINATOR wi 1 1:
6.3.2..1 Issue a-report, utilizing the guidance in Attachment 8, which addresses:
a.
Correlation of radiological release data.
b.
Dose assessment to, emergency response personnel and the public.
c.
Evaluation of environmental sampling program.
d.
Coordination of results with off-site agencies.
6.3.2,.2 Provide an initial assessment of the radiological impact to the public immediately following the emergency.
6.3.2.3 Establish a follow-up radiological assessment program.
6.4 RADIATION SUPPORT MANAGER Duties
,6.4.1 If the EOF was activated, the RADIATION SUPPORT MANAGER will:
6.4. 1. 1 Issue a report,.utilizing the guidance in Attachment B, which addresses:
EP-IP-038 Revision
Page 6 of 9 a..
Correlation of radiological release data.
b.
Dose assessment to emergency response personnel and the public.
c.
Evaluation of environmental sampling program.
d.
Coordination of results with off-site agencies.
6.4. 1.2 Provide an initial assessment of the radiological impact to the public immediately following the emergency.
6.4. 1.3 Establish a follow-up radiological assessment program.
6.5 The RADIOLOGICAL AND ENVIRONMENTAL SERVICES SUPERVISOR will review and approve all radiological reports associated with the emergency.
6.6 The VICE-PRESIDENT-NUCLEAR OPERATIONS will review and approve all reports associated with the emergency.
He-will also implement a
follow-up corrective action program, as appropriat Attachment A
EP-IP "038 Revision
Page 7 of 9 IN-PLANT'ADIOLOGICALCONSIDERATIONS A.l Characterize. radiation conditions that. existed in the plant.
o dose. rates o
airborne concentrations o-contamination levels o
identify radi.onuclide composition o
areas affected o
radioactive liquid inventory evaluate chemistry and radiological samples taken during emergency
..
A.2 Determine Personnel Exposures o
TLD Badges o
Self reading dosimeters o
reconstruct habitability conditions for occupied areas o
internal dosimetry program o
evaluate doses due to contamination o
evaluate extremity doses A.3 Characterize radiation conditions within the Restricted Area.
o vehicle surveys o
on-site buildings o
cooling tower samples/station blowdown Page 1 of
Attachment B
EP-IP"038 Revision
Page 8 of 9 OFF-SITE RADIOLOGICAL CONS IDERATIONS B.l. Correlate data to characterize the gaseous releases:
o effluent data o
meteorological data o
off-site. emergency monitoring team data o
Pressurized Ionization Chambers data o
air monitoring stations data o
REMP-TLDs data B.2 Correlate data to characterize the liquid releases:
o effluent data o
river samples, sediment and water B.3 Dose Assessment to Emergency Response Personnel o
TLD Badges o
Self reading dosimeters o
Air samples o
reconstruct habitability conditions for occupied areas o
internal dosimetry program B.4 Evaluate Environmental Sampling Program milk samples foodstuff samples o
drinking watersamples wildlife samples o
.domestic animal samples contamination estimates Page 1 of 2
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