ML20211G644
| ML20211G644 | |
| Person / Time | |
|---|---|
| Issue date: | 09/26/1997 |
| From: | Obrien J NRC (Affiliation Not Assigned) |
| To: | Chris Miller NRC (Affiliation Not Assigned) |
| References | |
| PROJECT-689 NUDOCS 9710030137 | |
| Download: ML20211G644 (19) | |
Text
September 26, 1997
- MEMORANDUM TO:
Charlss L. Mill:r, Chief Emergency Preparedness and Radiological Protection Dranch Division of Reactor Program Management, NRR FROM:
James B. O'Brien, EP Specialist Original signed ly:
Emergency Preparedness and Environment Health Physics Section Emergency Preparedness a id Radiological Protection Branch Division of Reactor Prograr i Management, NRR
SUBJECT:
SUMMARY
OF SEPTEMB iR 4,1997, MEETING WITH THE NUCLEAR ENERGY INST 6 TUTE ON EMERGENCY ACTION LEVEL GUIDANCE On September 4,1997, representatives of the Nuclear Energy Institute (NEI) met with representatives of the Nuclear Regulatory Commission (NRC) at the NRC's offices in Rockville, Maryland. Attachment 1 contains a list of meeting attendees.
The purpose of the meeting was to discuss NEl's revision to NUMARC/NESP 007, Revision 2, " Methodology for Development of Emergency Action Levels" which incorporates new guidance for emergency action levels applicable in the shutdown mode of plant operation. contains the slides from NEl's presentation. NEl plans to submit the revision to NUMARC/NESP-OO7 for NRC's review and endorsement.
Project No. 689 Attachments: As stated cc w/atts:
See next page QfO I
Distribution gCj E-Mail Hard Cooy M, O3 I
SCollins/FMiraglia
% Decket: Filet"s RZimmerman
- PUBLIC DMatthews PERB Reading File JGiitter RHasselburg SMagruder HTovmassian ODean OGC JMoore ACRS JRoe TMartin RAutuck MKnapp DOCUMENT NAME: G:\\EAL-MTG. SUM To rrctive a copy of this document, indicate in the box: "C' = Copy w/o attachment, "E" = Copy w/ attachment, "N" = No copy oFC EP&EHP/PERB b
(AlsC:EP&EF P/PERB b
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[8I NAME JBO'Br BZalcman 7 /Mf i7 9 /h/3 7
//
//
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DATE 9710030137 970926 FICIAL RECORD COPY.. L~
PDR REVGP ERON N C ll ll ll Illi llll 11 fRf? FRE t r COPY seu nos
September 26, 1997 MEMORANDUM TO:
Charl:s L. Miller, Chief Emergency Preparedness and Radiological Protection Branch Division of Reactor Program Management, NRR i
FROM:
James B. O'Brien, EP Specialist Original signc4 by:
Emergency Preparedness and Environment Health Physics Section Emergency Preparedness and Radiological Protection Branch f
Division of Reactor Program Management, NRR l
SUBJECT:
SUMMARY
OF SEPTEMBER 4,1997, MEETING WITH THE NUCLEAR ENERGY INSTITUTE ON EMERGENCY ACTION LEVEL GUIDANCE On September 4,1997, representatives of the Nuclear Energy institute (NEI) met with representatives of the Nuclear Regulatory Commission (NRC) at the NRC's offices in Rockville, Maryland. Attachment 1 contains a list of meeting attendees.
The purpose of the meeting was to discuss NEl's revision to NUMARC/NESP-OO7, Revision 2, " Methodology for Development of Emergency Action Levels" which incorporates new guadance for emergency action levels applicable in the shutdown mode of plant operation. contains the slides from NEl's presentation. NEl plans to submit the revision to IJUMARC/NESP-OO7 for NRC's review and endorsement.
Project No. 689 Attachments: As stated cc w/atts:
See next page Distribution E M ail Hard Coov SCollins/FMiraglia Docket File RZimmerrnan PUBLIC DMatthews PERB Reading File JGiitter RHasselburg SMagruder HTovmassian ODean OGC JMoore -
ACRS JRoe TMartin RAuluck MKnapp DOCUMENT NAME: G:\\EAL-MTG. SUM To receive a copy of this document. Indicate in the box: "C" = Copy w/o attachment. *E" o Copy wrattachment, "N" = No copy ol~c EP&EW*/PE,RB b
(AlsC:EP&EF P/PERB E
[8I NAME JBo'F,r BZaleman ffgnjkf 47 c) 1+ 1 7 ii ii ii OFFICIAL RECORD COPY I \\
sp ustoqA UNITED STATES I
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NUCLEAR REGULATORY COMMISSION g
WASHINGTON, D.C. 30e86 4001
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1 September 26, 1997 1
1 MC.MORANDUM TO:
Charles L. Miller, Chief Emergency Preparedness and Radiological Protection Branch Division of Reactor Program Management, NRR FROM:
James B. O'Brien, EP Specialist Emergency Preparedness and Environment Health Physics Section Emergency Preparedness and Radiological Protection Branch Division of Reactor Program Management, NRR
SUBJECT:
SUMMARY
OF SEPTEMBER 4,1997, MEETING WITH THE NUCLEAR ENERGY INSTITUTE ON EMERGENCY ACTION LEVEL GUIDANCE On September 4,1997, representatives of the Nuclear Energy Institute (NEl) met with representatives of the Nuclear Regulatory Commission (NRC) at the NRC's offices in Rockville, Maryland. Attachment 1 contains a list of meeting attendees.
The purpose of the meeting was to discuss NEl's revision to NUMARC/NESP-007, Revision 2, " Methodology for Developrnent of Emergency Action Levels" which incorporates new guidance for emergency action levels applicable in the shutdown mode of plant operation. contains the slides from NEl's presentation. NEl plans to submit the revision to NUMARC/NESP 007 for NRC's review and endorsement.
Project No. 689 Attachments: As stated cc w/atts:
See next page
,f
~.-
. -.-. ~. - - -.
NEl Project No. 689 cc:
Mr. Ralph Beedle Mr. Thomas Tipton, V ce President Senior Vice President Operations I-
. and Chief Nuclear Officer Nuclear Energy institute Nuclear Energy Institute Suite 400 l
Suite 400 1776 l Street, NW 1776 l Street, NW Washington, DC 20006 3708
[
. Washington, DC 20006 3708 4
Mr. Alex Marion, Director
- Mr. Jim Davis, Director Programs.
Operations l
Nuclear Energy Institute
- Nuclear Energy Institute Suite 400 Suite 400 1776 i Street, NW 1776 l Street, NW -
4 4
Washington, DC 20006 3708 Washington, DC 20000 3708 Mr. David Modeon, DireMor Ms. Lynnette Hendricks, Director Engineering Plant Support l
- Nuclear Energy institute Nuclear Energy Instituts
}
Suite 400 Suite 400 j
1776 i Street, NW 1776 i Street, NW j
Washington, DC : 20006-3708 Washington, DC 20006-3708 Mr. Anthony Pietrangelo, Director Mr. Nicholas J. Liparulo, Manager Licensing Nuclear Safety and Regulatory Activities
[
Nuclear Energy Instituto Nuclear and Advanced Technology -
j
- Suite 400 Division 1776 i Street, NW Westinghouse Electric Corporation Washington, DC 20006 3708
' P.O. Box 355 i
Pittsburgh, Pennsylvania 15230 i
Mr. Ronald Simard, Director Mr. Alan Nelson, Project Manager-L.
Advanced Technology -
Radiological Protection, Emergency -
l Nuclear Energy Institute -
Preparedness & Weste Regulation a
Suite 400 Nuclear Energy Institute 1776 i Street, NW Suite 400 Washington, DC _20006-3708 1776 i Street, NW -
Washington, DC 20006 3708 i
1 1
i l
2
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NRC/NEl MEETING ON EAL SCHEMES LIST OF ATTENDEES July 26,1996 I
NAME ORGANIZATION Alan Nelson NEl Steve LaVie Duquesne Light Co.
Tom Burns Com Ed Dennis Emborsky NU Frank Pavlechiw TVA Marv Luksic TVA Mtrick Bagan Supply System Theresa Sutter Bechtel Edward Wenzinger NUS Dave Stobaugh Com Ed Gary Cerkas Arizona Public Service Co.
Walter Lee Southern Nuclear James Jones Niagara Mohawk Tom Essig NRC/NRR Rich Hasselberg NRC/AEOD Harry Tovmassian NRC/RES Jim O'Brien NRC/NRR e
NEl PRESENTATION ON EMERGENCY ACTION LEVELS SEPTEMBER 4,1997
)
e NEl Emergency Action Levels for Shutdown Modes September,1997
- " *@N *
- E Assoentiena
\\
Overview I
l
>< incorporated into the NEl 97-03 Rev. 3 document (replacing NESP-OO7) t
>< Consistent with other NEl EALs
><Some changes made to existing NESP-007 EALs in NEl 97-03 Rev. 3 ANSDEAL1.PR3
j Status 1
- Some preliminary work with NRC staff during review and approval of NESP-007
'<lnitial draft prepared and issued for industry review
- Numerous comments led to re-structuring 2 Document issued for 2nd complete industry review in 1995 4
- Industry comments dispositioned i
alssued as final draft in NEl 97-03 rev. 3 in I
August 1997
$$ bkUt$0WR T1RtTgfRCy ACtIOR fat 0th ANSDEAL1PR3
l Shutdown Event Classification Challenges
- Plant configuration not the same as durinc power operation AEquipment not required to be operable while S/D.
- Equipment out-of-service for maintenance.
- <Oan vary from shutdown to shutdown and between periods in the same shutdown.
><Can't assume that equipment normally available at power will be available during shutdown.
i i
ANSDEAlt.PR3
~
Shutdown Event Classification Challenges i
i I
- Time since shutdown affects potential consequences
><A loss of RHR that occurs at the end of an extended outage has less impact than a loss that occurs during the first week.
i
>< Radiological source term inventory decreases with time -- majority of core inventory at time of S/D is short-lived.
N5IShutdown ' Emergency Action Levels
,g g,,,,
Shutdown Event Classification Challenges
><2 of 3 Fission product barriers may have been defeated
-><RCS open to containment - reactor head off
>< Containment may be open to the environment during many S/D operations.
ANSDEAlt.PR3
t Shutdown Event
~~~
Classification Challenges
>< instrumentation available at power may be disconnected
- e.g., core exit thermocouples are disconnected when the RX head is lifted i:PWR).
><lnstrumentation may be rendered inaccurate by conditions
><e.g., RCS loop temperature instruments are dependent of forced RCS flow I;PWR).
l Nff Sliutdown Emergency Action Leveh
.i Overview of Changes to NEl 97-03 (related to S/D issue)
><SD EAL discussion added to Chapter 3 of document ll
>< Operating mode applicability discussion l
in Chapter 3 upgraded w w.a-x,,,,nu,,u-a
=
Overview of Changes to NEl 97-03 (related to S/D issue)
><lnternal flooding EALs added to ICs HU1 and HA1, Natural and destructive l
Phenomena (mode =ALL)
>< Inadvertent Criticality IC (SU8) added
><lCs SA3, SU7, and SS5 deleted --
subsumed into the S/D EAL Matrix sw.,n x,,,,,, na-a-a
=
i 1
S/D Matrix R
i l
General Considerations
- Emphasis on performance of functions, j
rather than availability of equipment j
- <not technical specification operability
>< credit for any means to provide function l
>< Applicable mode is that which existed when event first detected.
><Cannot escalate into Fission Product i
Barrier Matrix
><Does not apply to defueled conditions ANSDEAL1.PR3 s
S/D Matrix initiating Conditions
- CU1
- CA1 Potential Loss of ANY ONE of Loss of ANY ONE of the the Following Functions Following Functions
>< RCS Inventory
>< RCS Inventory
>< Heat Removal
>< Heat Removal
- CS1 ACG1 Loss of ANYTHREE of the Loss of ALL the Following Following Functions Functions
>< Containment Closure
>< Containment Closure
>< RCS Integrity
>< RCS Integrity
>< RCS Inventory
- < RCS Inventory
>< Heat Removal
>< Heat Removal WIShutfoten Esnergency Actson Letre[s Ansoensens
e TABLE C-1 BWR Esnergency Action Level Cold Shutdown / Refueling Safety Function Matrix Determine which u..L;. L e of the four functione are lost or have a polertial lose and use the fosowing key priMded on the metric totde to closoffy the event UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY Potential Loos of ANY ONE of the following Loos of ANY ONE of the fo8cwing functione Loes of ANY THREE of the fA;s functione Loos of ALL the "his functione:
Cordainmerit Closure Coritamment Closure e
e RCS Inventory functione e
Heat Removal e
e e Heaf Removal Heat Removal Heat Removal e
THRESHOLDS FOR LOSS OR POTENTIAL LOSS OF FUNCTIONS HEAT REMOVAL CONTAINMENT CLOSURE LOSS POTENTIAL LOSS LOSS POTENTIAL LOSS RPV Level Cannot be Restored to UNPLANNED Loss of Function Direct Release Path Exists From Containment Atmosphere to the Not Applicable Above Top d Acilve FuelWithin Needed to Maintain Cold Shut-30 Minutes:
down indicated by-Environment OR
- 1. [ site specific] Indication That RCS Temperature Has Restoration d Functions Needed increased to Greater Than to Maintain Cold Shutdown Will be
[200*F].
RCS INTEGRITY a# AND [1 OR 2h LOSS POTENTIAL LOSS OR RCS Not intact Not Applicable
. [de c] Mcah N RCS Temperature Has
- 2. The Duration of the Function Increased to GfeaterThan Loss Has Exceeded [ site
[200*F].
specific] Time to Reach
[200*F] with RCS Temperature OR Indication Unsvailable.
RCS INVENTORY
[200*F] with RCS Temperature (Level 1) Setpoint Available RCS Makeup Capsbility Indication Unavailable.
5-C-5 Draft 7/5/97
\\
l l
TABLE C-2 PWR Emergency Action Level Cold Sleutdown / RefueIIng Safety Function Matrix Determine which combinations of the four functions are lost or have a pcdontialloes and use the following key presided on the matrix table to cleosify the evert UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY Potential Loss of ANY ONE of the fosowing Loos of ANY ONE of the following functions Loss of ANY THREE of the following functions Lossof ALLthefonowingfunctions functions e RCS inventory
. Contakwnent Closure
. RCSIntegrity e
e Heat Removat
- RCS Irwentory
. RCS trwentory e Heat Removal e Heat Removal THRESHOLDS FOR LOSS OR POTENTIAL LOSS OF FUNCTIONS CONTAINMENT CLOSURE HEAT REMOVAL LOSS POTENTIAL LOSS LOSS POTENTIAL LOSS Direct Release Path Exists From Loss of Reactor Vessel Levelin-UNPLANNED Loss of Function Containment Atmosphere to the Not Apphcable dicated by (1 or 2):
Needed to Maintain Cold Shut-Environrnent down indicated by-i 1.
[ site specific] Indication That Core Will Be Uncovered.
2.
Loss Exceeds [ site specific] Time "d
to Reach Core Uncovery With Has increased More Than Level WW UnavailaW.
RCS INTEGRITY 10*F Since Occurrence of LOSS POTENTIAL LOSS OR Loss.
OR UNPLANNED Loss of Function
[
RCS Not intact Not Applicable Needed to Maintain Cold Shut-down ic]
Time to Reach 10*F i
1.
[ site specific] Indication That RCS Increase With RCS Temperature Has increased More Temperature Indication Than 10*F and Exceeds [200*F].
Unavailable.
n ss LOSS POTENTIAL LOSS Has Exceeded [ site specific]
R actor Vessel Level Cannot be RCS Level Continuing to Time to Reach [200*F] With RCS Restored to Greater Than the Decrease AfterInitiation of Teh Indidim Bottom (ID) of the RCS Loop Available RCS Makeup Capability Unavailable Draft 7/5/97 5-C-10
-