ML20027C260
| ML20027C260 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 10/12/1982 |
| From: | Aidikoff B, Blauer H, Cordaro M, Lieberman E, Rivello J LONG ISLAND LIGHTING CO., STONE & WEBSTER ENGINEERING CORP. |
| To: | |
| Shared Package | |
| ML20027C225 | List: |
| References | |
| ISSUANCES-OL, NUDOCS 8210150206 | |
| Download: ML20027C260 (171) | |
Text
'
LILCO, October 12, 1982 l
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Board In the Matter of
)
)
LONG ISLAND LIGHTING COMPANY
) Docket No. 50-322 (OL)
) (Emergency Planning --
(Shoreham Nuclear Power Station,
) Phase I)
Unit 1)
)
TESTIMONY OF BRANT AIDIKOFF, H. MARK BLAUER, MATTHEW CORDARO, EDWARD LIEBERMAN, AND JAMES RIVELLO ON BEHALF OF THE LONG ISLAND LIGHTING COMPANY ON PHASE I EMERGENCY PLANNING CONTENTION EP 4 --
PROTECTIVE ACTIONS PURPOSE The purpose of thic testimony is to refute Suffolk County's Phase I emergency planning Contention EP 4, which asserts that LILCO lacks sufficient knowledge to make sound protective action recommendations -- that is, to advise Suffolk County officials to instruct the public to evacuate or to take shelter when a radiological emergency occurs or threatens to The substance of this testimony is that protective occur.
action recommendations depend on projections of offsite doce that are made during the early stages of an emergency and periodically during the course of the emergency.
When projected offsite doses exceed doses specified by a U.S.
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' l Environmental Protection Agency (EPA) Protective Action Guide
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(PAG), LILCO's procedures call for the company to recommend the
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l actions (sheltering or evacuation) specified by the PAG.
Consistency with the ETA PAG's is required by NRC regulations.
That the methods, systems, and equipment for making offsite i
dose projections are adequate is shovm by the LILCO testimony on a different contention, EP 14.
i Attachments to this Testimony:
4-1 Resume of Brant Aidikoff i
4-2 Resume of H. Mark Blauer 4-3 Resume of Matthew C.
Cordaro 4-4 Resume of Edward Lieberman 4-5 Resume of James Rivello 4-6 LILCO Emergency Plan section 6.4, " Protective Actions" 4-7 SP 69.013.01 Unusual Event 4-8 SP 69.014.01 Alert 4-9 SP 69.015.01 Site Area Emergency 4-10 SP 69.016.01 General Emergency 4-11 SP 69.022.01 Determination of Offsite Dose 4-12 SP 69.021.01 Onsite Surveys 4-13 SP 69.020.01 Downwind Surveys 4-14 SP 69.026.01 Protective Action Recommendations (presently l
undergoing revision) i i
_,__..__.-,_.,,____.____.,.m
. 4-15 SP 69.023.01 Thyroid Dose Commitment Using TCS Air Sampler 4-16 Pages 2.3 and 2.5 of EPA 520/1-75-001 4-17 SAND 77-1725, Appendices B and C i
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LILCO, October 12, 1982 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Board In the Matter of
)
)
LONG ISLAND LIGHTING COMPANY
) Docket No. 50-322 (OL)
) (Emergency Planning --
(Shareham Nuclear Power Station,
) Phase I)
Unit 1)
)
TESTIMONY OF BRANT AIDIKOFF, H.
MARK BLAUER, MATTHEW CORDAR0, EDWARD LIEBERMAN, AND JAMES RIVELLO ON BEHALF OF THE LONG ISLAND LIGHTING COMPANY ON PHASE I EMERGENCY PLANNING CONTENTION EP 4 --
PROTECTIVE ACTIONS Identifjcation of Witnesses Q1.
Will the witnesses please identify themselves?
A1.
[Aidikoff)
My name is Brant Aidikoff.
I am an Engineer - Power with Stone & Webster Engineering Corporation - New York.
My business address is One Penn Plaza, 250 West 34th Street, New York, New York 10119.
A copy of my professional qualifications is attached (Attachment 4-1).
My knowledge about this contention is based upon my assistance to LILCO in the development of LILCO's protective action recommendation procedure and my experience as detailed in my statement of professional qualifications.
1 l,
tBlauer)
My name is H. Mark Blauer.
My business l
address is 175 East Old Country Road, Hicksville, New York 11801.
I am LILCO's Emergency Planning Coordinator and Chairman of LILCO's Emergency Planning Task Force.
A copy of my professional qualifications is attached to this testimony (Attachment 4-2).
[Cordaro]
My name is Matthew C.
Cordaro.
I am Vice President, Engineering for LILCO.
My business addrest, is 175 East Old Country Road, Hicksville, New York 11801.
A copy of my professional qualifications j a attached (Attachment 4-3).
I am included on this witness panel to assure the ASLB that LILCO management regards emergency planning as of the utmost importance.
My role in emergency planning is to ensure that LILCO's emergency planning needs are being met and that
)
management is kept apprised of emergency planning needs and problems.
[Lieberman]
My name is Edward Lieberman.
My business address is 300 Broadway, Huntington Station, New York 11746.
I am a Vice President and principal of KLD Associates, Inc., which performs traffic planning studies for LILCO in connection with emergency planning for the Shoreham Station.
A copy of my professional qualifications is attached to this testimony (Attachment 4-4).
l [Rivello]
My name is James R1vello.
My business address is Shoreham Nuclear Power Station, P.O.
Box 628, Wading River, New York 11792.
I am employed by LILCO as Plant Manager of the Shoreham Station.
A copy of my professional qualifications is attached to this testimony (Attachment 4-5).
I am on this witness panel because it is my responsibility, upon receiving a recommendation from the Radiation Protection Manager in an emergency, to recommend protective actions to State and County officials, Contention EP 4 Q2.
What is EP 4?
A2.
[Aidikoff, Blauer)
Contention EP 4, as modified by the Atomic Safety and Licensing Board's Supplemental Prehearing Conference Order of September 7, 1982, reads as follows:
EP 4: PROTECTIVE ACTIONS (SC, joined by NSC and SOC)
Suffolk County contends that LILCO has not met the requirements of 10 CFR
% 50.47(b)(10), 10 CFR Part 50, Appendix E,
Item B, or NUREG 0654, Item II.J with respect to development and implementation of a range of protective actions for emergency workers and the public within the plume exposure pathway EPZ and with respect to development of guidelines for the choices of such actions in that the LILCO plan and procedures do not adequately discuss the bases for the
[
choice of recommended protective actions (i.e.,
the choice between various ranges of evacuation vs. sheltering vs. other options) for the plume exposure pathway i
EPZ during emergency conditions.
- Thus, I
LILCO does not have sufficient knowledge and information to provide reliable, accurate protective action recommendations.
t Q3.
What appears to be the crux of this contention?
l A3.
[Aidikoff, Blauer]
The fundamental proposition of the i
contention is that LILCO has not adequately discussed the " bases" for choosing which protective actions to recommend.
In explaining its Contention EP 4.A, counsel for Suffolk County, in an August 5, 1982 letter to LILCO
{
counsel, said the following:
CONTENTION EP [4].
As we understand 10 C.F.R. 550.47(b)(lO) and NUREG 0654, Item i
II.J, LILCO is required to set forth in its plan a " range of protective actions" and discuss the " bases" for making recommendations within that range under various emergency conditions.
In our view I
LILCO has failed to do so.
Had LILCO done so, we assume it would have been possible for one to assess the relative benefits of i
the various protective actions which would i
be set forth in the plan.
f An implicit part of this contention, apparently, is that i
there is no " discussion of the relative benefits of I
sheltering in the types of homes found on Long Island,"
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as the County put it on page 9 of its August 30, 1982, i
response to LILCO's and the NRC Staff's objections to j
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the Phase I contentions.
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LILCO Emergency Plan Q4.
Where in the LILCO emergency plan are protective actions i
discussed?
A4.
[Aidikoff, Blauer)
In section 6.4,
" Protective Actions."
A copy of that section is attached to this testimony as Attachment 4-6.
The crux of that section is the following:
LILCO will make a protective action recommendation to Suffolk County and.New York State authorities for.the population at risk.
The various protective action options available are detailed in the New York State and Suffolk County emergency response plans.
The protective action recommendation is based upon dose projection calculations, field monitoring data, EPA protective action guidelines t sheltering factors offered by local dwellings and evacuation time estimates for ambient conditions.
The emergency plan procedure, " General Emergency" immediate implementing actions, contains protective actions to be recommended during events that are deteriorating rapidly based upon conditions in accordance with NUREG 0654, Appendix 1.
The details of this decision process are contained in the EPIPs.
[ Emphasis added.)
Thus, the " bases" for protective actions that the County alleges the LILCO plan does not adequately discuss are the following:
1.
Dose projection calculations, 2.
Field monitoring data, 3.
EPA protective action guides, 4.
Sheltering factors offered by local dwellings, and 5.
Evacuation travel time estimates for a ranga of local conditions.
We believe that the County intends to litigate nos.
3, 4,
and 5 of these bases under EP 4.
As for the other two, the dose projectiron calculations are discussed under Contention EP 14, " Accident Assessment and Dose Assessment Models," and the field monitoring data are discussed under Contention EP 10, Accident Assessment and Monitoring."
Former contention EP 22, Accident Assessment Equipment," has rot been admitted to this proceeding.
The Board has indicated that some of the issues raised by former contention EP 1 (local conditions) may be addressed under this contention (EP 4) or under EP 14.
t QS.
The discussion in LILCO plan section 6.4 is somewhat limited.
Please give additional information about how LILCO will go about making protective action recommendations.
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[Aidikoff, Blauer]
The information in the plan is brief because NUREG-0654 states that the plan should be concise.
NUREG-0654 on page 29 states this:
Applicable supporting and reference documents and tables may be incorporated by reference, and appendices should be used whenever necessary.
The plans muld be kept as concise as possible.
The plan is not an implementing document that is actually used in an emergency.
Rather it is a summary document that lays out the basic elements of the plan for the benefit of reviewers such as the NRC Staff.
The working details of how protective action recommendations are made are contained in th^ emergency plan implementing procedures.
For each of the four emergency classifications (Unusual Event, Alert, Site Area Emergency, General Emergency) (see SP 69.013.01, 69.014.01, 69.015.01, and 69.016.01), the procedure for calculating projected offsite doses, SP 69.022.01, is initiated, and in the case of an Alert, Site Area Emergency, or General Emergency, an onsite survey is performed using SP 69.021.01.
Additional personnel are requested to report to sugment the onsite staff in the case of an Alert or higher level emergency.
If the protected offsite Cose calculation or the onsite survey indicates the need for it, the downwind survey procedure I
(SP 69.020.01) is initiated.
It is the projected offsite doses, measured or calculated in accordance with these procedures, that are used to determine protective action recommendations under SP 69.026.01.
- Also, SP 69.023.01, Thyroid Dose Commitment Using TCS Air Sampler," provides instructions for obtaining a thyroid dose commitment value from field team survey results.
These procedures are Attachments 4-7, 4-8, 4-9, 4-10, 4-11, 4-12, 4-13, 4-14, and 4-15 to this testimony.
This testimony is based upon a revision of SP 69.026.01 that is now in progress; a copy oi~the revised procedure will be submitted to the Board as soon as it is ccmpleted and approved. -14 is the present version of SP 69.026.01, before the revision has taken f
place, but is still useful to illustrate the methods I
discussed in this testimony.
Appendix 1 of NUREG-0654 says that predetermined protective actions should be established for rapidly developing General Emergency initiating conditions.
In Appendix 6.1 of SP 69.016.01 (Attachment 4-10) LILCO has developed protective action recommendations based only upon plant conditions, to be used when there is insufficient time available to complete the other previously mentioned procedures.
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In short, what are needed to make protective action recommendations are (1) the projected offsite doses and (2) the EPA Protective Action Guides that describe which actions should be taken when the projected doses reach certain specified levels.
LILCO's ability to make the offsite dose projections is addressed in LILCO's testimony on Contention EP 14.
Protective Action Guides Q6.
So in this testimony you are going to talk about EPA's Protective Action Guides.
What are " Protective Action Guides"?
A6.
[Aidikoff, Blauer]
The EPA defines a protective action guide (PAG) on page 1.1 of its Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, EPA 520/1-75-001, September, 1975 (revised June 1980):
After a nuclear incident occurs, an estimrate is made of the radiation dose which affected population groups may potentially receive.
This dose estimate is called the projected dose.
A protective action is an action taken to avoid or reduce this projected dose when the benefits derived from such action are sufficient to offset any undesirable features of the protective action.
The Protective Action Guide (PAG) is the projected dose to individuals in the population which warrants taking protective action.
Q7.
What is a Protective Action Recommendation?
A7.
(Blauer, Aidikoff]
A Protective Action Recommendation (PAR) is a recommendation from LILCO to State and County officials to implement protective actions (either sheltering or evacuation) that will reduce the exposures that might otherwise occur.
It is a governmental responsibility to implement these protective actions.
In no case can LILCO give such an order directly to the public.
Q8.
How does LILCO arrive at a Protective Action Recommendation?
A8.
[Blauer, Aidikoff]
In order to reflect changes in plant or meteorological conditions, LILCO continually determines the projected dose to downwind zones using either calculations or field monitoring procedures.
Using the projected dose as an input into the Protective Action Recommendation procedure SP 69.026.01, the thyroid and whole body doses to the population at risk are determined for each of the protective actions under consideration.
The results of these calculations are shelter doses and evacuation doses for whole body and thyroid exposure.
These doses are compared to the EPA Protective Action Guides as follows:
. t No action is recommended in Emergency Response l
Planning Areas (ERPA's) where the projected whole body dose is less than 1 rem or the projected i
thyroid dose is less than 5 rem.
Sheltering is recommended in ERPA's where the projected dose is 1 to 5 rem whole body or 5 to 25 rem thyroid; evacuation will be recommended if as the accident develops it becomes clear that the evacuation dose would be less than the sheltering dose.
l Evacuation is recommended in ERPA's where the evacuation dose is less than the sheltering dose and the sheltering dose is greater than 5 rem whole body and greater than 25 rem thyroid:
Q9.
Where did you get these dose guidelines?
A9.
[Aidikoff, Blauer)
The dose guidelines come from the Environmental Protection Agency's Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, EPA 520/1-75-001, September 1975 (revised June 1980).
The relevant pages, pages 2.3 and 2.5, containing Tables 2.1 and 2.2, are Attachment 4-16 to this testimony.
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. Q10.
Who told 'ou to use the EPA PAG's?
AlO.
[Aidikoff, Blauer]
The NRC.
Section 50.47(b)(10) of 10 C.F.R.
reads as follows:
(b) The onsite and offsite emergency response plans for nuclear power reactors must meet the following standards
[ footnote omitted):
(10) A range of protective actions have been developed for the plume exposure pathway EPZ for emergency workers and the public.
Guidelines for the choice of protective actions during an emergency, consistent with Federal guidance, are developed and in place, and protective actions for the ingestion exposure pathway EPZ appropriate to the locale have been developed [ emphasis added).
a i
Similarly, NUREG-0654, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," Rev.
1, Item II.J (page 60 of the document) says this:
7.
Each licensee shall establish a mechanism for recommending protective actions to the appropriate State and loca.'.
authorities.
These shall include Emergency Action Levels corresponding to projected dose to the population-at-risk,
)
in accordance with Appendix 1 and with thq
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recommendations set forth in Tables 2.1 and 2.2 of the Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (EPA-520/1-75-001).
As specified in Appendix 1, prompt notification shall be made directly to the offsite authorities responsible for implementing protective measures within the plume exposure pathway Emergency Planning Zone [ emphasis added].
1 l
.. Thus, 10 C.F.R. 9 50.47(b)(10) says that guidelines for protective actions are to be " consistent with Federal guidance."
NUREG-0654 says that tha nechanism for recommending protective actions should be in accordance with EPA'a Manual of Protective Action Guides.
Qll.
Are you aware of any commercial nuclear power plants in this country that do not employ the same EPA PAG's that LILCO uses?
All.
[Blauer, Aidikoff]
No.
Sheltering Q12.
What factors determine how effective a building is at shielding a person from radioactivity?
A12.
[Aidikoff, Blauer]
The principal factors for whole body dose are (1) the building materials (stone or wood frame) and (2) whether the house has a basemert.
For thyroid dose tne principal factor is the infiltration rate of outside air into the interior of the house.
Q13.
What sheltering factors do you use for different buildings?
A13.
[Aidikoff, Blauer]
For the whoJe bcdy dose, representive shielding factors are listed in Appendix 12.4 to SP 69.026.01 (Attachment 4-14).
For the purpose
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of this procedure LILCO will use a 0.7 shielding factor for houses in Suffolk County.
The shielding factors in i
SP 69.026.01 are based on a document called "Public i
Protection Strategies for Potential Nuclear Reactor Accidents:
Sheltering Concepts With Existing Public and i
Private Structures," SAND 77-1725 (printed February f
1978), by David C.
Aldrich, David M.
- Ericson, Jr.,
and J. D.
Johnson, prepared by Sandia Laboratories.
For thyroid dose a dose reduction of two-thirds is assumed for the first two hours.
This is based upon information in the EPA Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, EPA 520/1-75-001, September, 1975 (revised June, 1980); EPA, 1
l
" Protective Action Evaluation, Part I, The Effectiveness of Sheltering as a Protective Action Against Nuclear i
Accidents Involving Gaseous Releases," EPA 520/1-78-001A i
(April 1978) by George H. Anno and Michael A. Dore; and
" Protective Action Evaluation, Part II, Evacuation and
[
t Sheltering as Protective Actions Against Nuclear Accidents Involving Gaseous Releases," EPA 520/1-78-001B i
(April 1978, revised 8-78), by George H. Anno and i
Michael A. Dore.
i Q14.
Are the sheltering factors from SAND 77-1725 used in the i
i emergency plans for other nuclear power plants in this Country?
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A14.
[Aidikoff, Blauer]
Yes, they are used by many other nuclear power plants, including Zimmer, Salem, and River Bend.
Q15.
How are these shielding factors incorporated into the protective action recommendations that LILCO makes?
A15.
[Aidikoff, Slauer]
The projected dose is reduced by the amount of protection offered by the type of structures for whole body dose and the standard amount for thyroid dose.
Q16.
Have you determined a Suffolk County-specific sheltering factor based upon the Sandia Labs report?
A16.
[Aidikoff, Blauer]
Yes.
We contacted the Suffolk County Planning Department, and they informed us that about 75% of Suffolk County homes have basements and about 90% are wood frame.
LILCO weighted the SAND 77-1725 sheltering factors with these data and determined that a shielding factor of 0.7 is representative of the Suffolk County area.
This is consistent with SAND 77-1725, which indicates that housing in the Northeast offers the most protection (see Appendices B and C of SAND 77-1725, which are Attachment 4-17 to this testimony).
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l Evacuation Time Estimates l
Q17.
You testified that another basis of your protective action recommendations is the evacuation time estimates.
How did LILCO use evacuation time estimates in setting up the thyroid guidance chart and whole-body guidance chart in Appendix 12.5 of SP 69.026.01?
A17.
[Aidikoff, Blauer]
SP 69.026.01 (Attachment 4-14, prior to revision) as a procedure for evaluating to what extent the projected dose will be reduced by implementing various protective actions.
The evacuation time estimates are used to determine how long the population at risk might be required to stay within the plume during an evacuation and what the consequent dose might be.
This " evacuation dose" is compared to a
" shelter dose," and the protective action guides are utilized to determine a recommended protective action.
Q18.
What is the basis for the evacuation time estimates in Appendix 12.3 of SP 69.026.01?
A18.
[Aidikoff, Blauer, Lieberman]
These estimates were developed by Suffelk County Planning Department personnel and were reviewed by KLD Associates.
This review considered the assumptions and estimates employed and determined that the resulting time estimates were
- ~ - - - - - - - - - - - -
__ reasonable.
The KLD work is continuing and may be submitted as evidence in Phase II of the litigation of emergency planning issues, depending on what contentions are raised in Phase II.
If because of new information the evacuation time estimates are revised, the only change to SP 69.026.01 will be to the tables of evacuation times; the procedure will remain the same.
Range of Protective Actions Q19.
Are LILCO's procedures flexible enough to allow you to recommend partial evacuation (that is, evacuation of only certain sectors or evacuation of only certain especially vulnerable groups of people such as children and pregnant women) to the offsite authorities?
What about selective sheltering (sheltering of individuals who may be more adversely affected by evacuation than by potential contamination)?
A19.
[Aidikoff, Elauer]
LILCO's procedures provide for the projection of doses in each downwind sector out to 2, 5,
or 10 miles.
Thus it is possible to provide a i
prctective action recommendation specifically determined for each of these areas.
The County or State may choose i
to limit the recommendation to selected portions of the i
public.
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Conclusions:==
Compliance with NRC l
Regulations and Guidance I
l Q20.
In your judgment, has LILCO complied with 10 C.F.R. 50.47(b)(10), which is quoted earlier in this testimony?
I A20.
[Aidikoff, Elauer, Cordaro, Rivello]
Yes, a range of protective actions for each of the downwind sectors han l
[
been developed for the plume exposure pathway EPZ for j
the public.
Guidelines for the choice of protective actions during an emergency are developed and in place, in SP 69.026.01 (Attachment 4-14, prior to revision).
They are consistent with federal guidance, namely the EPA Protective Action Guides.
The evacuation time i
estimates are developed for downwind combinations of the t
19 ERPA's.
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i Q21.
What does 10 C.F.R. Part 50, Appendix E, Item IV.B, say?
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A21.
[Blauer, Aidikoff]
That part of Appendix E reads, in
[
i pertinent part, as follows:
i B.
Assessment Actions.
The means to be used for determining the magnitude of and for continually assessing l
the impact of the release of radioactive materials shall be described, including the eraergency action levels that are to be used for determining when and what type of protective measures should be i
considered.
outside the site boundary to protect health and safety.
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.i Q22.
Do LILCO's plans for recommending protective actions to the offsite authorities comply with 10 C.F.R. Part 50, Appendix E?
A22.
[Aidikoff, Blauer, Cordaro, Rivello]
Yes.
As specified in IV.B of Appendix E, the emergency action levels that are to be used for determining when and what type of protective measures should be considered within and 1
outside the site boundary to protect health and safety i
are de ribed in the LILCO plan and procedures.
Q23.
What about protective actions for " emergency workers"?
A23.
[Aidikoff, Blauer)
Apart from the words " emergency workers" in the contention, we have seen no indication that the County wishes to litigate protection of emergency workers within the scope of Contention EP 4.
A different contention, EP 9(C), addresses guidelines for ensuring that emergency workers do not receive excessive radiation exposures.
Therefore, this EP 4 testimony does not address protective actions for emergency workers.
Q24.
What about the " ingestion exposure pathway"?
A24.
[Aidikoff, Blauer]
The County has not indicated a desire to address the ingestion pathway under Contention EP 4.
Therefore this testimony does not address the ingestion pathway.
f 4
I L L Q25.
What about protective action guides for waterborne releases?
A25.
[Aidikoff, Blauer]
The County has not indicated any desire to litigate issues about waterborne releases.
Therefore this testimony does not address waterborne i
releases.
Q26.
Are LILCO's plan and procedures consistent with l
NUREG-0654, Item II.J?
?
A26.
[Aidikoff, Blauer]
Yes.
In particular, LILCO's plan and procedures comply with Item II.J.7, which recommends e
that each licensee establish a mechanism for recommending protective actions to the appropriate State
[
and local authorities and which is the only part of l
II.J. that the County appears to have put into 1
contention.
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- - 1 PROFESSIONAL QUALIFICATIONS BRANT AIDIKOFF Engineer - Power Division l
STONE & WEBSTER ENGINEERING CORPORATION 1
My name is Brant Aidikoff.
My business address is Stone & Webster Engineering Company (SWEC), 1 Penn Plaza, 250 West 34th Street, New York, New York 10119.
I am currently f
involved with Nuclear Power Plant Emergency Planning. I have been employed by SWEC since 1979.
I was awarded a Bachelor of Science degree in Energy j
Conversion in 1975 and a Master of Engineering degree in 1976, both from Cornell University.
I am currently the Responsible Engineer for the group providing emergency planning support for LILCO's Shoreham Nuclear Power Station (Shoreham).
This effort involves detai-4 led reviews of the Shoreham emergency plan and corresponding procedures.
As a result of these reviews, my group developed i
an emergency organization, emergency plan sections, and imple-f menting procedures. In addition, all non-radiological Emergency Action Levels were developed for use in emergency clas-i sification.
Presently, a comprehensive training and drill pro-t gram is being implemented to prepare for an emergency response exercise to be witnessed by the Nuclear Regulatory Commission.
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l Prior to my involvement with this group, I led two groups that prepared radiological emergency response Standard I
Operating Procedures (SOPS) for the Radiation Control Branch in the State of Kentucky and the Clermont County Disaster Services Agency in Ohio. These SOPS contained overall descriptions and i
detailed instructions for the State's emergency response to the offsite radiological aspects of an accident at a nuclear power plant.
Procedures were provided for notificationP mobilization, offsite dose projection, radioactive release monitoring and sampling, equipment use, and decontamination.
l This effort involved extensive interaction with State officials responsible for radiation control and emergency response.
I coordinated the development of the offsite dose projection methodology for the Zimmer Nuclear Power Station and for the States of Ohio and Kentucky.
I also led a task force that directly supported the i
efforts of PSE&G of New Jersey to respond to the NRC Appraisal Program Findings prior to Salem II licensing.
This support consisted of a reevaluation of Salem's emergency organization, Emergency Action Levels, and protective action recommendations; development of a personnel training program and associated documentation; and a complete review of all documents and plans for consistency.
My support included meeting with NRC Region I representatives to explain the direction and intent of PSE&G's efforts.
This task force played a significant role in the successful licensing of Salem II Generating Station.
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' I also led the development of the Emergency Plan Implementing Procedures (EPIPs) for the W.
H.
Zimmer Nuclear Power Station. This effort consisted of developing a set of procedures that would direct the Station and Corporate emergency response personnel in their responsibilities during an accident.
Frequent dealings with site, corporate, and con-tractor personnel were necessary.
In addition, I have led the efforts that developed radiological procedures for the States of New Jersey and Delaware.
These efforts were noted for the timeliness with which they were effected and the delicacy of the dealings with State officials.
Documents produced have been in accordance with numerous regulatory guides, including NUREG-0654/ FEMA REP 1,
FEMA REP 2, NUREG-0696, and EPA Manual of Protective Action Guides.
These documents, in support of PSE&G's Salem Nuclear Power Station, have been submitted to FEMA.
I was also responsible for the FSAR Section 13.3 Emergency Plan for the Gulf States Utility River Bend Station Nuclear Power Plant.
The project involved writing the site emergency plan based upon applicable NRC and FEMA regulations; development of the emergency response organization; and coordi-nation of required technical and geopolitical input.
This document is presently undergoing final ptyearation for FSAR submittal to the NRC.
Moreover, I coordinated the initial development of the emergency plan implementing procedures.
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This effort consisted of a comprehensive liaison with the plant i
operating staff to develop site-specific procedures that would be used by the emergency personnel during an emergency event.
i I continue to be a member of the Stone & Webster i
Corporate Group that reviews emergency plans developed for var-ious nuclear utilities. This group analyzes the emergency plans i
for content and acceptability relative to currently applicable l
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NRC and FEMA regulations.
I am a registered Engineer-in-Training in the State of r
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L PROFESSIONAL QUALIFICATIONS
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MARK BLAUER Chairman, Emergency Planning Task Force Emergency Planning Coordinator
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LONG ISLAND LIGHTING COMPANY My name is H. Mark Blauer.
My business address is Long
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Island Lighting Company, 175 East Old Country Road, Hicksville, New York 11801.
I am Chairman of the Emergency Planning Task I
Force and Emergency Planning Coordinator.
In this capacity, I report to the Vice Presdient, Nuclear, and the Vice President, f
Engineering.
I also report to the Manager, Nuclear Engineering r
Department.
My duties include overall technical and adminis-l tration responsibility for the Emergency Planning Task Force.
j The Task Force is responsible for developing and maintaining the Shoreham Nuclear Power Station Emergency Plan; Emergency Training curriculum, manuals, and lesson plans; qualification i
and selection of emergency response personnel; Emergency Plan I
i procedures; onsite and offsite emergency support facilities; the Prompt Notification System; the interfacing with Federal (NRC, DOE, FEMA, Coast Guard), State (Department of Health, t
Disaster Preparedness Commission) and Local (Suffolk County, r
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- hospitals and fire departments) authorities as well as other nuclear industry support groups (INPG).,
I received my Bachelor and Master of Science degrees from the State University of New York at Stony Brook in 1968 and 1971, respectively.
I received my Doctorate in Nuclear Chemistry from the University of Glasgow, Scotland in 1977.
From 1971 to 1975 I was a Research Assistant (U.S.
equivalent:
Aasistant Professor) at the University of Glasgow teaching nuclear chemistry and researching low-level tritium techniques.
I was a Research Assistant (U.S. equivalent:
Assistant Professor) at University College, London from 1975 to 1977 teaching isotope geology, researching major and trace ele-ment techniques and acting as consultant to several water auth-orities.
During this period the following were published:
- Anderson, A.,
- Blauer, H.
M.
and Baxter, M.S. (1977). A controlled power supply for the electrolytic enrichment of tritium, J.
Physics, V10, pp. 1286-1294.
Beckinsale, R.D.,
- Bowles, J.F.W.,
Pankhurst, R.J.,
Wells, M.K.
and Blauer, H.M.
(1977).
I Rubidium-strontium age studies and geochemistry of acid veins in the Freetown cor. plex, Sierra Leone, Mineralogical Magazine, V41, pp. 501-511.
- Blauer, H.M.,
- Baxter, M.S.
and Anderson, A.
(1978).
An improved technique for the electrolytic enrichment of tritium, Analyst, V103, pp. 823-829.
- Hope, C.A.,
Blauer, H.M.
and Reiderer, J. (1980).
Recent analysis of 18th dynasty pottery in "Studien zur Altagyptischen Keramic," edited Dorothea Arnold, Philip i
von Zabern, Mainz.
i l
In 1977 I returned to the United States and assumed the i
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position of Assistant Professor at the University of 1
Pittsburgh, Department of Radiation Health from 1977 to 1980.
j I taught radiation health, radiation chemistry and nuclear j
chemical separation techniques; researched bioassay techniques i
and low-level environmental measurement techniques; directed an l
EPA certified radio-chemical laboratory; and consulted with j
several major uranium producers.
During this period the fol-l lowing were published:
i Dennis, Nancy A.,
- Blauer, H. Mark, and Kent, Jacqueline E.
(1981).
Dissolution fractions and half-times of single source yellowcake in simulated lung fluids, Health Physics, V41.
- Culp, P.
and Blauer, H.M.
(1979).
Dissolution rates of radionucleides from coal and coal ashes, Twenty-fourth Annual Meeting of the Health Physics Society, Philadelphia, PA.
f
- Dennis, N.A.
and Blauer, H.M. (1979).
Dissolution rates of uranium in yellowcake in simulated lung fluids, Twenty-fourth Annual Meeting of the Health j
Physics Society, Philadelphia, PA.
Padezanin, T.
and Blaucr, H.M. (1979).
Comparison of uranium urinalysis methods, Twenty-fourth Annual i
Meeting of the Health Physics Society, Philadelphia, PA.
Blauer, H.M.
and Dennis, N.A.
(1979).
Dissolution rates of uranium from single source yellowcake in both 1
simulated interstitial and surfactant lung fluids, 4
Twenty-fifth Annual Conference on Bioassay, Enviromental and Analystical Chemistry, Las Vegas, N.Y.
l I
- Maitz, A.H.
and Elauer, H.M.
(1980).
Pure uranium oxides:
their dissolution rates plus relationship to yellowcake dissolution characteristics, Twenty-fifth Annual Meeting of the Health Physics Society, Seattle, WA.
j
- Blauer, H.M.
and Brown, S.H.
(1980).
Physical and
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chemical parameters affecting dissolution I
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i characteristics of yellowcake in simulated lung fluids, Twenty-fifth Annual Meeting of the Health Physics i
Society, Seattle, WA.
- Brown, S.H.
and Blauer, H.M.
(1980).
Characterization j
of yellow-cake (U308) from multiple sources and some implications regarding uranium mill bioassay, Twenty-f fifth Annual Meeting of the Health Physics Society, i
Seattle, WA.
t From 1980 to 1981 I was Environmental Scientist at l
Three Mile Island Nuclear Generating Station responsible for
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audits, the Radiological Environmental Monitoring Program, f
i offsite dose calculations and health effects studies.
During f
this period the following positions and procedures were writ-ten:
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j Blauer, H. Mark (1981).
Three Mile Island Nuclear
[
j Station, Comments on the Articles "The First Casualty at TMI" and "The Lethal Path of TMI Fallout" by Ernest J.
Sternglass.
I Blauer, H. Mark (1981) TMI Enviromental Controls REMP Procedure, Determination of REMP investigation levels and subsequent actions, ECP 1507, Rev.
1.
Blauer, H. Mark (1981) TMI Environmental Controls i
Emergency REMP Procedure, operating procedure for the
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J Blauer, H. Mark (1981) TMI Environmental Controls i
Emergency REMP Procedure Determination of Off-Site Dose, ECP 1602, Rev.
1.
Blauer, H. Mark (1981) TMI Environmental Controls Procedure Ge(li) detector system using series 80, ECP 1719, Rev.
O.
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I joined LILCO in 1981 as Senior Scientist, Nuclear i
Licensing Division.
My responsibilities include providing sup-port to corporate and plant staff in the areas of Radiation
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Protection, Health Physics, ALARA, Emergency Planning and REMP.
In 1982 I became Chairman of the Emergency Planning Task Force
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responsible for all technical and administrative functions.
i During this period, the following courses and procedures were j
prepared:
i i
General Physics - BWR Familiarization Course (1 week)
[
1 LILCO - BWR Familiarization Course (2 weeks) i 1
Blauer, H. Mark (1981) Anomalous data results - LLD and j
positive value exceptions, RP 4.3, Rev. O
- Blauer, H. Mark (1982) Acceptance Criteria, RP 4.4, Rev. O
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Blauer, H. Mark (1982) Determination of REMP investiga-
[
tion levels and subsequent actions, RP 4.5, Rev.
O.
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am certified by the American Chemical Society and a
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I membe'r of the American Geophysical Union and Health Physics t
Society.
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' - 3 PROFESSIONAL QUALIFICATIONS MATTHEW C.
CORDARO Vice President of Engineering LONG ISLAND LIGHTING COMPANY My name is Matthew C.
Cordaro.
My business address is Long Island Lighting Company, 175 East Old Country Road, Hicksville, New York 11801.
I am currently Vice President of Engineering and have held this position since the spring of 1978.
As Vice President of Engineering, I am responsible for all of LILCO's engineering activities.
This includes responsi-bility in the areas of facility planning and engineering for nuclear and fossil electric generating plants, as well as elec-tric and gas transmission and distribution systems.
In addi-tion, I am responsible for assessing the environmental impacts of all LILCO operations.
I received my Bachelor of Science degree in Engineering Science from C. W.
Post College in 1965.
I received my Master i
of Science degree in Nuclear Engineering from New York University in 1967. I received my Doctorate in Applied Nuclear Physics from the Cooper Union School of Engineering and Science
(
in 1970.
I was awarded the Atomic Energy Commission Special Fellowship in Nuclear Science and Engineering.
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My past professional affiliations include a position as i
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q Adjunct Associate Professor of Nuclear Engineering at Polytechnic Institute of New York and Adjunct Assistant j
Professor at C. W.
Post College.
i I joined LILCO in 1966 and from 1966 to 1970 I held the i
a positions of Assistant Engineer (1966), Associate Engineer (1967), Nuclear Physicist (1968) and Senior Environmental 1
Engineer (1970).
In these earliest positions with LILCO I was 1
I involved as a principal in all phases of nuclear power plant design, licensing and fuel management.
I was also a lead wit-i
]
for the Company in Federal and State licensing proceedings ness 1
for the Shoreham and Jamesport Nuclear Power Stations.
In 1972 I assumed the position of Manager of Environmental Engineering.
In this capacity I was responsible for the environmental impact of all LILCO operations.
This position involved the supervision, administration and direction of all environmental progrmas aimed at demonstrating compliance I
with applicable standards.
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I am a member of a number of related professional i
organizations including: the Board of Directors, Adelphi University's Center on Energy Studies; and the Council of Overseers, C. W.
Post College.
Other related professional
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the Technical Resources Advisory Council to
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Forces and Committees of the Atomic Industrial Forum; the Long 1
Island Association of Commerce and Industry Environmental j
Committee; the Advisory Board to Environmental Technology f
f Seminar; the Environment and Energy Committee of the Edison i
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Electric Institute; and the HSA Environmental Task Force.
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have also been a member of the Research Planning Advisory f
I Committee for the New England River Basins Commission Study o#
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Long Island Sound, the Marine Advisory Council to the New York 4
l State Sea Grants Seminar, and the Nassau-Suffolk Health Systems i
l Agency (HSA), Suffolk County Council.
In addition, I am a member of the American Nuclear Society, the Health Physics Society and the Environmental Technology Seminar.
My most recent publications include a paper on methodology for power plant site selection, papers presented at the World Energy Conference on space heating alternatives and 2
power plant cooling systems, a paper related to power plant l
waste heat utilization, and a paper on the transportation of nuclear wastes.
I have also published journal articles in the fields of environmental science and nuclear science, as well as 4
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I recently testified before Congressional Committees on Nuclear Waste Transport and the Economics and Environmental l
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Impacts of Coal Utilization.
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- - 4 PROFESSIONAL QUALIFICATIONS EDWARD L1EBERMAN Vice President KLD ASSOCIATES, INC.
My name is Edward Lieberman and my business address is KLD Associates, Inc., 300 Broadway, Huntington Station, New York 10007.
I am presently Vice President of KLD Associates, Inc.
I received my Bachelor of Science degree in Civil Engineering in 1951 from Polytechnic Institute of Brooklyn.
I was awarded my Master of Science degrees in Civil Engineering in 1954 from Columbia University and in Aero Engineering in 1967 from Polytechnic Institute of Brooklyn.
I subsequently worked on a Doctorate degree in Transportation Planning at Polytechnic Institute of New York.
I am a member of Chi Epsilon Honorary Fraternity.
With almost 30 years of professional experience, I have managed numerous major projects.
I pioneered the development and application of traffic simulation models, making major innovations in the state-of-the-art in the Traffic Engineering profession.
I have also been responsible for many engineering studies involving data collection and analysis and design of traffic control systems to expedite traffic flow and relieve congestion.
I have developed simulation models to study traffic i
performance on urban networks, freeways, and freeway corridors.
I am currently working on a traffic simulation model for two-lane, two-way rural roads.
These programs include consideration of pedestrians' interaction with vehicular traffic, truck and bus operations, special turning lanes, and vehicle fuel consumption and emissions; both pretimed and actuated traffic signal controls are represented.
I was responsible for the theoretical development of DYNEV, a Dynamic Network Evacuation model.
The DYNEV model consists of two major components:
an equilibrium traffic assignment model and a macroscopic dynamic traffic simultation medel designed for all types of roadway facilities (urban streets, freeways, rural roads).
DYNEV is designed to be used as a tool to develop and organize evacuation plans needed as part of general disaster preparedness planning.
DYNEV was used to analyze an existing evacuation scenario at the Con Edison Indian Point Nuclear Power Station and is currently being used to develop an extensive evacuation plan for the LILCO Shoreham Nuclear Power Station on Long Island, New York.
In developing this evacuation plan for LILCO's Shoreham Nuclear Power Station, my activities include definition of evacuation scenarios, definition of the evacuation network,
-3 j
development of traffic control treatments and of traffic routing patterns, analysis of trip tables, analysis of simulation results, optimization of evacuation strategies and the preparation of formal documentation.
I was also responsible for the designs of the NETSIM microscopic urban traffic simulation model (formerly UTCS-1) and of the SCOT freeway traffic simulation model.
The NETSIM microscopic traffic simulation model developed for the Federal Highway Administration, enables agencies to evaluate traffic operations in urban environments.
The SCOT model was developed for the Transportation Systems Center of the Department of Transportation.
This program includes a dynamic traffic assignment algrithm which routes traffic over a network in response to changing traffic flow characteristics to satisfy a apecified origin-destination table.
In addition, I have developed advanced traffic control policies for urban traffic for the FHWA-sponsored UTCS Project, as well as a bus preemption policy to enhance the performance of mass transit operations within urban environs.
I designed and programmed the advanced " Third Generation" area-wide, cycle-free control policies for moderate and congested traffic flow for computer-monitored real-time systems.
I also developed a cycle-based, off-line computational procedure named SIGOP-II, to optimize traffic signal timing patterns to minimize system "disutility."
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I led a group of traffic engineers and systems analysts f
l in developing a system of macroscopic traffic simulation models i
designed to evaluate Transportation Systems Management (TSM)
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This software syctem, named TRAFLO, also includes an equilibrium traffic assignment model.
This model has been f
i distributed to other agencies including FEMA.
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I designed an " Integrated Traffic Simulation System,"
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named TRAF, which will eventually incorporate all the best i
i traffic simulation models available.
Using structured i
i programming techniques, TRAF will integrate:
NETSIM, TRAFLO, j
r INTRAS (a microscopic freeway traffic simulation model), and a I
i microscopic rural-road simulation model.
t I served as Principal Investigator on NCHRP Project i
3-20 entitled, " Traffic Signal Warrants."
This project
[
i involved both field data collection and the application of the I
NETSIM model to study intersection delay as a function of l
h traffic volume, type of control and geometrics.
In turn, I I
r developed and documented new signal warrants which wil be l
l incorporated in the next version of the Manual on Uniform f
I Traffic Control Devices (MUTCD).
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Under NHTSA sponsorship, I directed a research study to i
t evaluate a Driver Vehicle Evaluation Model named DRIVEM.
This t
I model simulates the resonse of motorists to hazardous events.
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A workshop was designed, organized, scheduled and conducted by myself and other KLD professionals; experts from all over the U.S. were invited to recommend specific NHTSA research activities for the further development of the model.
A recommended research program constituted the major output of the contract.
Over the years I have been involved in a number of other studies to evaluate traffic operations on large-scale road networks, using one or more of the models described above.
Prior to 1960 I applied my skills to the areas of stress analysis, vibrations, fluid dynamics and numerical analysis of differential equations.
These analyses were programmed for the IBM 7090 and System 360, CDC 6600 and 7600, j
G.E. 625 and UNIVAC 1108 digital computers in assembly j
language, FORTRAN and PLI.
I also designed the logic and real-time programming for a sonar simulator built for the Department of Navy and monitored by a PDP-8 process-control digital computer.
f I am a member of the American Society of Civil Engineers, the Institute of Transportation Engineers, the Association of Computing Machinery and the Transportaton Research Board (TRB).
I am also a member of the Capacity Committee and of the Traffic Flow Thecry and Characteristics Committee of the TRB.
I am a licensed Professional Engineer in New York, Maryland, and Florida.
5,
The following list comprises selected publications of j
my studies and findings:
"DYNET - A Dynamic Network Simulation of Urban Traffic Flow," Proceedings, Third Annual Simulation Symposium, 1970.
" Simulation of Traffic Flow at Signalized Intersections: the SURF System," Proceedings, 1970 i
Summer Computer Simulation Conference, 1970.
" Dynamic Analysis of Freeway Corridor Traffic," ASME paper, Trans. 70-42.
" Simulation of Corridor Traffic:
The SCOT Model,"
" Highway Research Record No. 409, 1972.
" Logical Design and Demonstration of UTCS-1 Network Simulation Model," Highway Research Record No. 409, l
1972 with R. D. Worrall and J. M.
Bruggerman).
" Variable Cycle Signal Timing Program:
Volumes 1-4,"
Final Report of Contract DOT-FH-11-7924, June, 1974.
" Traffic Signal Warrants," KLD TR-51, Final Report on NCHRF Proj ect 3-20/1, December 1976 (with G.
F.
King and R. Goldblatt).
" Rapid Signal Transition Algorithm," Transportation Research Record No. 509, 1974 (with D. Wicks).
"Subnetwork Structuring and Interfacing for UTCS Project-Program of Simulation Studies," KLD TR-5, January, 1972.
" Development of a Bus Signal Preemption Policy and a System Analysis of Bus Operations," KLD TR-11, April 1973.
"SIGOP-II - Program to Calculate Optimal, Cycle-Based Traffic Signal Timing Patterns, Volumes 1 and 2,"
Final Report, Contract DOT-FH-11-7924, KLD TR-29 and TR-30, December 1974.
Summary report in Transportation Research Record 596, 1976 (with J.
Woo).
" Developing a Predictor for Highly Responsive i
System-Based Control," Transportation Research Record t
596, 1976 (with W. McShane and R.
Goldblatt).
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~ "A New Approach for Specifying Delay-Based Traffic Signal Warrants," Transportation Research Special Report 153 - Better Use of Existing Transportation Facilities, 1976.
" Network Flow Simulation for Urban Traffic Control Systems," Vols.
1-5, PB230-760, PB230-761, PB230-762, PS230-763, PB230-764, 1974 (with R. Worrall). Vols. 2-4 updated 1977, KLD TR-60, TR-61, TR-62 (with D. Wicks and J. Woo).
" Extension of the UTCS-1 Traffic Simulation Program to Incorporate Computation of Vehicular Fuel Consumption and Emissions," KLD TR-63, 1976 (with N. Rosenfield).
" Analysis and Comparison of the UTCS Second-and Third-Generation Predictor Models," KLD TR-35, 1975.
" Urban Traffic Control System (UTCS) Third Generation Control (3-GC) Policy," Vol.
1, 1976 (with A. Liff).
" Design of TRAFIC Operating System (TOS), KLD TR-57, 1977.
" Revisions to the UTCS-1 Traffic Simulation Model to Enhance Operational Efficiency," KLD TR-59, 1977 (with A. Wu).
"The Role of Capacity in Computer Traffic Control," in Research Directions in Computer Control of Urban Traffic Systems, ASCE, 1979.
" Traffic Simulation: Past, Present and Potential," in Hamburger, W.S.
and Steinman, L.,
eds., Proceedings of the International Symposium of Traffic Control Systems, Unversity of California, Berkeley, 1979.
"TRAFLO:
A New Tool to Evaluate Transportation System Management Strategies," presented at the 59th Annual Meeting of the Transportation Research Board, 1980 (with B. Andrews).
" Determination of the Lateral Deployment of Traffic on an Approach to an Intersection," presented at the 59th Annual Meeting of the Transportation Research Board, 1980.
8-
" Service Rates of Mixed Traffic on the Left-Most Lane of an Approach," presented at the 59th Annual Meeting of the Transportation Research Board, 1980 (with W.
R.
McShane).
" Development of a TRANSYT-Based Traffic Simulation Model," presented at the 59th Annual Meeting of the Transportation Research Board, 1980 (with M. Yedlin).
" Hybrid Macroscopic-Microscopic Traffic Simulation Model," presented at the 59th Annual Meeting of the Transportation Research Board, 1980 (with M. C.
i Davila).
"A Model for Calculating Safe Passing Distance on Two Lane Rural Rcad," presented at the 60th Annual Meeting of the Transportation Research Board, 1981.
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PROFESSIONAL QUALIFICATIONS JAMES RIVELLO Plant Manager i
LONG ISLAND LIGHTING COMPANY My name is James Rivello.
My business address is Long Island Lighting Company, Shoreham Nuclear Power Station, P.
O.
Box 628, Wading River, New York 11792.
I am Plant Manager of the Shoreham Nuclear Power Station and have held this position since 1978. I am responsible for managing all plant activities in a manner which provides efficient overall plant operation and ensures the generation of the maximum amount of electric power at the highest plant efficiency, reliability, and availa-bility. This objective must be achieved at the most economical cost consistent with prudent managen ent.
I am also responsible for ensuring that all plant activities are conducted in compli-ance with plant technical specifications, licenses, QA, nuclear safety, radiation control, health physics, environmental, secu-rity, and other factors.
Plant operations must meet Nuclear Regulatory Commission (NRC), Federal, State, and Company Requirements, with the minimum radiation exposure to the gen-eral public and employees.
I delegate responsibility to four subordinate Engineers.
Each of these Engineers is responsible
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for a particular facet of the plant operations requiring speciali=ed knowledge and ability, and for coordinating their I
activities with those of the other Engineers to create a re-f sponsive and cohesive plant organization.
I represent the Shoreham Plant in engineering, construction and testing activi-ties as well as technical licensing efforts with federal, state i
and local regulatory groups.
I formulate all policies to oper-ate the nuclear plant within the requirements specified in the Technical Specifications, FSAR, Title 10 Code of Federal l
Regulations and other industry standards and guidelines.
In the event of an accident I am Emergency Director of the Plant.
I also chair both the Review of Operations Committee, which ap-proves the performance of all safety related aspects of the P
plant, and the Joint Test Group during the Preoperational Phase to overview the Startup Staff Test Program.
I graduated from Manhattan College in 1963 with a i
Bachelor of Mechanical Engineering degree.
I completed two I
years of the Nuclear Engineering Masters Program at Long Island l
j University C. W. Post Campus (1967-69).
In 1973 I completed specialized nuclear courses at the University of Michigan.
I I
have also completed courses conducted by the General Electric
[
Company in BWR Technology (August 1973) and BWR Simulator and i
e have received Senior Reactor Operator Certification (December 1973).
6
, J Before assuming my present position, I was Startup c
Manager for the Shoreham Station (1974-1978).
I developed the l
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Startup Program, the Implementing Manual, and the Checkout and Initial Operations Test Program.
My responsibility was to co-ordinate engineering, construction, and plant staff activities i
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l as they relate to system completion regarding design, construc-tion, documentation of testing and compatibility of generated i
i data in the respective organizations. I directly managed six I
Engineers, including the S&W lead Advisory Engineer, the General Electric Company Site Operations Manager, and four Lead Startup Engineers.
t From December 1973 to November 1974 I was assigned to t
Commonwealth Edison Company's Dresden Nuclear Station as a f
i Technical Staff Engineer (five months) and Proj ect Engineer j
(six months).
As a Technical Staff Engineer, one of my major duties was coordination of a refueling outage of D-3, not in-cluding basic maintenance work.
I worked directly for the Lead t
Nuclear Engineer and Assistant Plant Manager., I participated r
in post refueling outage startup testing which included neutron I
monitoring overlap tests, flux shaping safety relief valve ca-pacity tests, etc.
I also provided substantial input to plan-ning for the refueling outage of D-2 as a result of my past ex-f f
perience on D-3.
I performed all activities of Technical Staff i'
Engineer from unusual event reports (abnormal occurrences) to major and minor modification safety evaluations, engineering, l
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procurement, and operaticnal testing (e.g.,
off-gas system installation and startup, SBLC and HPCI, surveillance tests, shutdown margin tests, fuel sipping, RC pump " freeze plug" re-pair, integrated leak rate test, jet pump calibration, refuel-ing jib crane replacement, control rod friction testing, nuclear materials safeguards program, hydraulic snubber inspec-tions, torus level instrumentation replacement, etc.).
As a Project Engineer, I was directly responsible for the final construction schedule and initial operations testing of a major high conductivity drain waste concentra-j tion / evaporation system.
I conducted and evaluated all tests 1
on this system and recommended and implemented changes and met the EPA in-service date.
I coordinated operator training on system operations and ran the system for ona month under heavy demand conditions.
Throughout this assignment, I performed many substantial projects for the onsite review committee and special nuclear systems testing and evaluations including, for example, evaluation of off-gas system explosions and installa-tion of new Safety Relief Valves (Target Rock).
From April 1971 to May of 1973 I was Chief Engineer (Assistant Plant Manager) of a multi-unit 400 MW fossil fueled station.
From June 1963 to May 1971 I held supervisory posi-tions in four different fossil fueled stations, following the 1
normal progression of Associate Engineer (entry level for engineers), Plant Engineer, Operating Engineer, Maintenance and I&C Engineer.
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? -6 Additionally, EPIP describes subsequent and/or supplemental corrective actions for the scope of potential situations within each of the
(
emergency classifications.
These EPIPs are designed to guide the actions of personnel to correct or mitigate a condition as early and as near to the source of the problem as feasible. Specific actions are described, for example, which may prevent or significantly reduce a potential release of radioactive material, provide for prompt fire control and ensure timely damage control and repair. These procedures are also utilized as emergency training media and are the basis for periodic emergency drills.
6.4 Protective Actions 6.4.1 Offsite Actions The EPIP gives the details of which offsite authorities will be notified for each emergency class, information to be provided in accordance with the New York State Notification Fact Sheet and Dose Assessment Fact Sheet and verification practices to be used.
LILCO will make a protective action recommendation to Suffolk County and New York State authorities for the population at risk.
The various protective action options available are detailed in the New York State and Suffolk County emergency response plans.
The protective action recommendation is based upon dose projection calculations, field monitoring data, EPA protective action guidelines, sheltering factors offered by local dwellings and evacuation time estimates for ambient conditions.
The emergency plan procedure,
(
" General Energency" immediate implementing
- actions, contains protective actions to be recommended during events that are deteriorating rapidly based upon conditions in accordance with NUREG 0654, Appendix 1.
The details of this decision process are contained in the EPIPs. Regarding the protective actions taken on behalf of the general public, notification will be made of ar. emergency situation via the use of the Prompt Notification System set up throughout the ten (10) mile Emergency Planning Zone (EPZ).
This notification system, installed by LILCO, will be operationally tested and functional prior to fuel load and consistent with the criteria set forth in Appendix 3 to NUREG-0654.
Although the utilisation of this system is the responsibility of Suffolk County (individual operating and administrative responsibilities for this system are described fully in the County's Emergency Response Plan Procedures), the system shall be maintained by LILCo. This system, made up of sirens fcr general population coverage and tone activated radios for special facilities (i.e.,
hospitals, nursing homes, nursery schools, etc.), shall alert the public within the 10 mile EPZ of a possible nuclear int:ident.
Upon notification of an emergency to the general public via the Prompt Notification System, the public shall be directed by previously disseminateo information to tune to a specific radio station and await
(
6-11
l e
informative instruction on what protective actions such as sheltering evacuation, if any, should be taken for their respective Emergency or
(
Response Planning Area.
I Informative pamphlets shall be located in strategic locations such as gas stations, motels and resorts for the purpose of supplying the transient population with emergency information. Public notification and education are reviewed in great detail in Section 8.4.
Evacuation routes are defined in the Suffolk County Emergency Plan:
however. maps of the EP2 and population distribution, in a sector l
format, are located on Figures 6-2 and 6-3, respectively.
As stated above, notification to the pub 3ic as a whole will be made 2
via the siren warnin'g system.
Incorporated into this system for the purpose of notifying those organizations with a large number of personnel, such as large businesses, hospitals, etc.,
are separately i
- operated, tone-activated, alert radios which would be in accordance 4
with the appropriate County procedures.
At the same time, the population would be notified of the need for evacuation, buses would be dispatched to evacuate schools and special institutions, and road blocks would be set up for the purpose of restricting in-coming traffic in accordance with the Suffolk County Radiological Emergency l
Response Plan.
The basis for the choice of recommended protective actions from the plume exposure pathway is shown in the EPIP. Time estimates for the evacuation of the 10 mile EPZ are as delineated as in the attachment i (
to LILCO's submittal to the NRC in SNRC-488, dated August 7,1980 and i
as amended by the information found in Appendix C.
6.4.2 Plant Site Action Protective action within the plant site will be initiated by actual or imminent radiological conditions or other habitability hazards such as toxic gas or fire. Upon assessment by the Emergency Director that a situation exists that requires evacuation of areas of the plant, an evacuation signal will be activated simultaneously with an announcement of the emergency condition over the party page system indicating the areas to be evacuated. Evacuated personnel will report to designated assembly areas consistent with implementing procedures.
When personnel have assembled, personnel accountability will then proceed following the guidance of the personnel accountability procedures.
Accountability for onsite personnel will be accomplished within 60 minutes.
l In the event of a site evacuation, Figure 6-1 details the onsite 4
assembly areas with primary and secondary evacuation routes leading to the LILCO main access road. Transportation for onsite personnel shall be by personal vehical as well as car pooling where conditions warrant.
6-12 s
,.,,__.,____m
~. =. -. _ _ _. _. _ _ _ _ _ _ _ _. _ _ _ _ _. _ _, _ _ _ ~,, _.. _.. _. _ _. - _ _
l i
cvacuntien, if cny, cheuld be teksn for th2ir respretiva Emergancy er Response Planning Area.
i
~
L7LCO will provide supporting informatiop for the preestablished written messages intended for the public to be disseminated by Suffolk 34 County or New York State officials. These messages, consistent with the classification system described in Section 4 of this Plan are detailed in Appendix F.
Informative pamphlets shall be located in strategic locations such a.s gas stations, motels'and resorts for the purpose of supplying the transient population with emergency information. Public notification and education are reviewed in great detail in section 8.4.
defined in the Suffolk County Emergency Plan:
Evacuation routes are however, maps of the EPZ and population distribution, in a sector format, are located on Figures 6-2 and 6-3, respectively.
As stated above, notification to the public as a whole will be made via the siren warning system.
Incorporated into this system for the purpose of notifying those organications with a large number of are separately personnel, such as large businesses, hospitals, etc.,
- operated, tone-activated, alert radios which would be in accordance with the appropriate County procedures.
At the same time, the pepulation would be notified of the need for evacuation, buses would be dispatched to evacuate schools and special institutions, and road l
biceks would be set up for the purpose of restricting in-ccming traffic in accordance with the Suffolk County Radiological. Emergency Resp:nse Plan.
The basis for the choice of recommended protective actions from the plume exposure pathway is shown in the EPIP. Time estimates for the evacuation of the 10 mile EPZ are as delineated as in the attachment to LILCO's submittal to the NRC in SMRC-488. dated August 7,1980 and as amended by the information found in Appendix C.
6.4.2 Plant Site Action Protective action within the plant site will be initiated by actual or imminent radiological conditions or other habitability hacards such as toxic gas or fire. Upon assessment by the Emergency Director that a situation exists that requires evacuation cf areas of the plant, an evacuation signal will be activated simultaneously with an announcement of the emergency condition over the party page system indicating the areas to be evacuated.
Evacuated personnel will report to designated assembly areas consistent with implementing procedures.
When personnel have assembled, personnel accountability will then proceed following the guidance of the personnel accountab.lity procedures.
Accountability for onsite personnel will be accomplished 34
,within 30 minutes.
6-12
The extent and nature of personnel and vehicle monitoring will depend on the amount and physical nature of the radioactive material released.
If personnel exit the site via the portal monitors in the guardhouse, monitoring can be considered complete.
If background levels preclude use of the portal monitors, monitoring should be performed at the offsite assembly area.
If vehicle monitoring is perfo rmed, it should be performed along the LILCO main access road at the 69KV substation. Vehicles found to be contaminated should be directed into the substation for decontamination.
Individuals remaining on site or arriving on site following an emergency evacuation should be reporting to either the Control Room, Technical Support Center, or the operational Support Center. These emergency response facilities shall have emergency equipment as described in Section 7.4.1 and Appendix E, including respiratory protective equipment, protective clothing, and radioprotective drugs.
l Areas within the site boundary to which the public has access and l
which may require evacuation, include a small portion of the Wading River Creek marsh, the shorefront and jetties along the north boundary of the site, and the summer camp (St. Joseph's Villa, operated by the Diocese of Brooklyn) located on the Shoreham West property.
Notification to the personnel at these locations would be achieved through use of the Prompt Notification System discussed in Section 6.4.1.
Should conditions warrant at the discretion of the Emergency Director, notification to these public access areas shall be made by plant personnel through the use of public telephone, and/or the dispatch of a station employee with a power megaphone within 30 I
minutes of such a determination.
The initiation and implementation of protective actions are the responsibility of New York State and Suffolk County agencies. LILCO's responsibilities include:
1.
The timely notification of agencies.
2.
The assessment activities including dispatch of radiation monitoring teams needed to verify the estimated offsite censequences of radiation releases.
3.
The providing of all information needed by the agencies for estimating offsite risks.
A detailed breakdown of the actions required to notify those persons requiring evacuation and the time sequence, is shown and completely L
detailed and reviewed in the Suffolk County Plan.
Following any large scale releases of radioactive material on site, access control points shall be established at those locations bounding the area (s) contaminated in excess of 1000 dpm/100 cm2 If large area contamination exists that precludes use of the 1000 dpm/100 cma
- criteria, then the Radiation Protection Manager, with the Emergency Director, shall establish an initial ingress and egress point to the
(
6-13
Shoreham site that allows frisking and access control of personnel entering and exiting the site.
A secondary control point (e.g.,
I Security Gate) inside the contaminated areas shall be established to provide a gross frisk for personnel contamination, and a security control of personnel entering the normal plant site environs. Food l
and water supplies shall be provided from ' areas outside the access control boundaries.
The water shall be bottled and the food bagged.
Specific areas inside the access control boundaries will be maintained j
at less than 1000 dpm/100 cm2 loose surface Beta, Gamma radioactivity and less than 1x10 ' uCi/cc of Beta, Gamma airborne activity.
Areas and items will be permitted return to normal use upon declaration of end of the emergency condition by the Emergency Director and f
concurrence by the Radiation Protection Manager.
To the extent possible, emergency conditions permitting the normal contamination limits established in Health Physics procedures will be utilized.
6.5 Aid to Affected Personnel 6.5.1 Emergency Personnel Exposure Criteria j
l All reasonable measures shall be taken to maintain 'the radiation dose to emergency personnel as low as reasonably achievable and within 10 CFR Part 20 limits.
Personnel performing emergency activities involving exposures which may or will exceed 10 CFR 20 limits shall be volunteers and shall be briefed on potential expcsure consequences
)
prior to receiving such dese.
Authorization to exceed 10 CFR 20 limits shall be made only by the Emergency Director and/or the Radiation Protection Manager. Since this authorization is made only
(
during declared emergencies, this capability is readily avcilable on a 24-hour a day basis (see Section 5.1).
Emergency Exposure Criteria, detailed in the Emergency Plan Implementing Procedures, are consistent with EPA Emergency Worker and Lifesaving Activity Protective Action Guides (EPA 520/1-75-001).
Table 6-4 depicts Emergency Exposure Criteria for various activities.
6.5.2 Decontamination To the extent possible, the normal station contamination limits shall be adhered to.
The personnel contamination limits are 100 cpm above background as measured by an RM-14/HP-210 cr equivalent. Equipment contamination limits are less than 200 dpm/100 cm2 removable Beta, Gamma.
Decontamination of emergency personnel wounds, supplies, instruments and equipment shall normally be conducted in the Personnel Decentamination Facility adjacent to the Health Physics office on the 15' elevation of the Turbine Building. This facility contains showers with controlled drains and the necessary materials for personnel decontamination. The Personnel Decontamination Facility contains a stainless steel sink and decen area which shall be used for contaminated minor wounds, equipment and instruments.
6-14
(
s l'
l
_shall be established at those locations bounding the area (s) contaminated in excess of 1000 dpm/100 cm2 If large area contamination exists that precludes use of the 1000 dpm/100 cmr l
criteria, then the Radiation Protection Mana*ger, with the Emergency Director, shall establish an initial ingress and egress point to the shoreham site that allows frisking and access control of personnel entering and exiting the site.
A secondary control point (e.g.,
Security Gate) inside the contaminated areas shall be established to c..
provide a gross frisk for personnel contamination, and a security control of personnel entering the normal plant site environs.
Food and water supplies' shall be provided from areas outside the access control boundaries. The water shall be bottled and the food bagged.
Specific areas inside the access control boundaries will be maintained at less than 1000 dpm/100 cm2 loose surface Beta, Gamma radioactivity and less than 1x10 S uCi/cc of Beta, Camma airborne activity. Areas and items will be permitted return to normal use upon declaratien of i
end of the emergency condition by the Emergency Director and concurrence by the Radiation Protection Manager.
To the extent possible, emergency conditions permitting the normal contamination limits established in Health Physics procedures will be utilized.
6.5 Aid to Affected Personnel G.5.1 Emergency Personnel Exposure Criteria All reasonable measures shall be taken to maintain the radiation dose to emergency personnel as low as reasonably achievable and within 10 CFR Part 20 limits.
Personnel performing emergency ' activities involving exposures which may or will exceed 10 CFR 20 limits shall be volunteers and shall be briefed on potential exposure consequences prior to receiving such dese.
Authorization to exceed 10 CFR 20 limits shall be made only by the Emergency Director and/or the Radiation Protection Manager.
Since this authorization is made only during declared emergencies, this capability is readily available on a 24-hour e day basis (see Section 5.1).
Emergency Exposure Criteria.
detailed in the Emergency Plan Implementing Procedures, are consistent with EPA Emergency Worker and Lifesaving Activity Protective Action Guides (EPA $20/1-75-001).
Table 6-4 depicts Emergency Exposure Criteria for various activities.
All personnel entering or werking within the radiologically controlled Restricted Area shall be issued a Direct Reading Desimeter and a g4 Thermoluminescent Dosimeter (TLD) subject to provisions contained in normal station hea'th physics procedures. A TLD reader is maintained onsite to provide for 24 hr. per day capability to determine deses received by personnel.
6.5.2 Decontamination To the extent possible. the normal station contamination limits shall be adhered to.
The personnel contamination limits are 100 epm abcVe background as measured by an RM-14/HP-210 or equivalent. Equipment 6-14
- -7 4-
,3 l
Submittsd:
'~'
Raviewed/0QA gr w;
Revision _0
(
Approved / Plant Mgr.:
Date Eff 7/09/82 5
l UNUSUAL EVENT i
[
1.0 CONDITION i
1.1 An UNUSUAL EVENT has been declared based on the occurrence of events Mieli f
indicate a potential degradation of the level of safety of the plant, as described in SP 69 010.01, Classification of Emergency Action Levels.
2.0 IMMEDIATE ACTIONS 2.1 For All Initiating Events
(
2.1.1 Control Room Operator, implement corrective actions to contend with
[
the situation and to mitigate possible deterioration in plant a
conditions in accordance with the SNPS Operating Procedures while simultaneously implementing this procedure.
2.1.2 Control Room Operator, announce over the page/ party system the following:
I 2.1.2.1 "The plant is in an UNUSUAL EVENT condition' - repeat.
L 2.1.2.2 The location or general area affected.
2.1.2.3 Any operations / wor'x to be halted.
i i
2.1.2.4 Specific instructions to plant personnel as apolicable.
2.1.3 Emergency Director, direct the Communicator to fill out a l
Notification Fact Sheet, (Appendix 12.1 of SP 69 009 01, f
Notifications, using data derived from the initial assessment
[
activities.
t 2.1.4 Communicator, implement SP 69 009 91, Notifications after receiving l
l' the approved Fact Sheet from the Emergency Directcr in order to' I
I 2.1.4.1 Notify offsite agencies.
i 2.1.4.2 Notify additional station emergency response personnel as needed.
r 2.1.4.3 Notify the LILOO offsite emergency response organization.
I i
i e
I t
4
.-0 2.1.5 Parform any of tha following as nacessary:
i 2.1.5.1 Airborne Release - Section 2.2 I
2.1.5.2 Waterborne Release - Section 2.3 2.1.5.3 Fire / Explosion - Seetion 2.4 2.1.5.4 Personnel Injury - Section 2.5 4
2.1.5.5 Natural Event - Section 1.6 2.7 For Initiating Event: Airborne Release 2.2.1 Inplant Radiation Monitoring Technician or designee, initiate and continue offsito dose projection activities as necessary in-accordance with SP 69 922,.01, Determination of Offsite Doses.
2.3 For Initiating Event: Waterborne Release
)
2.3.1 In plant Rsdiation Monitoring Technician, determine the activity of I
the release by effluent monitor reading, or by estimate in accordance with normal station procedures.
2.3.2 In plant Radiation Monitoring Technician, initiate SP 69 924.91, j
Waterborne Release Dose Projection.
2.4 For Initiating Event:
Fire / Explosion
.(
2.4.1 Control Room Operator, upon receipt of a report of a fire or valid alarm, direct fire brigade members to perform fire fighting efforts in controlled areas in accordance with the SNPS Fire Flan.
2.5 For Initiating Event: Personnel Injury i
2.5.1 Control Room Operator, upon receipt of a report of injury / illness implement SF 69.949 91, Personnel Injury or if a missing individual's location is not known, implement SP 69 989 91, Search and Rescue.
2.6 For Initiating Event: Natural Event 2.6.1 Operations personnel, perform emergency measures. in accordance with SP 29 991.91, Acts of Nature 3.0 SUBSEOUCNT ACTIONS 3.1 Emergency Director, direct the Communicator to fill out a Dose Assessment Fact Sheet (Appendix 12.2 of SP 69 999 91, Notifications), using the most current data available at the time the form is completed.
3.2 When offsite agencies call back, Control Room Communicator provide SP 69 913.91 Rev. 9
(
7/09/82 Page 2
information from tha approvad Dose Assassment Fact Shast as appliccble to the emergency condition. Accept calls and provide information to only those organizations listed on the notification call-lists.
Refer all other calls to LILCO public affairs personnel.
(
3.3 Emergency response personnel, perform emergency measures in accordance with the appropriate Emergency Plan Implementing Procedures (SP 69.xxx.xx series) and Emergency Operating Procedures (SP 29.xxx.xx series).
3.4 If plant conditions deteriorate, Emergency Director reclassify the emergency in accordance with SP 69 919 91, Classification of Emergency Action Levels.
1 3.5 Emergency response personnel, continue emergency operations, including assessment activities, until such time as plant conditions have stabilized.,
and other termination criteria of CIP-19 Recovery, have been satisfied.
i l
l 4.0 FINAL CONDITIONS 4.1 Emergency measures are continuing for the Unusual Event, the emergency has been reclassified or the emergency has been terminated.
4.2 For initiating events related to Limiting Conditions of Operation (LCOs),
the emergency condition can be considered terminated when the appropriate actions specified in the " action' section of the LCO have been taken, and all notifications have been completed.
5.0 DISCUSSION
(
5.1 Once an Unusual Event condition has been declared at SNPS in accordance with SP 69 019.01, -Classification of Emergency Action Levels, this procedure guides the Emergency Director in the performance of major actions and provides reference to other applicable Emergency Plan Implementing Procedures for further actions and more detailed instructions.
5.2 In the event of emergency conditions not adequately covered by this procedure, the Emergency Director has the responsibility and authority to take whatever action he considers required to prevent injury to personnel 4
or damage to the plant or to equipment and to place the plant in a safe condition.
6.0 APPENDICES N/A l
SP 69 913.91 Rev. 9
(
7/09/82 Page 3 I
l
/
. - 8 Submitted:
1 M
SP Numbar:
69.014.01 M
f Reviewed /OQK Engr.:
j bo Revision:
1
(
Approved / Plant Mgr.:
Date Eff.:
7/09/82 ALERT l
l 1.0 CONDITION j
1.1 An ALERT has been declared based on the occurrence of events which indicate i
an r.etual or potential degradation of the level of safety of the plant, as described in SP 69 010.01, Classification of Emergency Action Levels.
l l
2.0 IMMEDIATE ACTIONS 2.1 For All Initiating Events 2.1.1 Control Room Oprator, implement corrective actions to contend vl'.h the situation and to mitigate possible deterioration in plant conditions in accordance with SNPS Operating Procedures while (1
simultaneously implementing this procedure.
2.1.2 Control Room Operator announce over the page/ party system the following:
2.1.2.1 The plant is in an ALERT condition 2.1.2.2 The location or general area affected
- (
2.1.2 3 Any operations / work to be halted
-2 2.1.2.4 Specific instructions to plant personnel as applicable 2.1.3 Emergency Director, direct a Communicator to fill out Notification l
Fact Sheet (Appendix 12.1 of SP 69 009.91, Notifications) using l
data derived from the initial assessment activities.
t 2.1.4 Communicator implement SP 69 999 91 Notifications af ter receiving the approved Fact Sheet from the imergency Director in order to:
l 2.1.4.1 Notify offsite agencies 2.1.4.2 Notify additional station emergency response personnel as needed i
i 2.1.4.3 Notify the LILCO offsite emergency response organization 2.1.5 Emergency Director notify the Shift Security Supervisor to:
<1 2.1.5.1 Implement SP 9x.xxx.xx, OSC Access Control W
2.1.5.2 Implement SP 9x.xxx.xx, TSC Access Control i
a l
l
2.1.6 Parform any of the following as nicessary:
<1 2.1.6.1 Airborne Release - Section 2.2 2.1.6.2 Waterborne Release - Section 2.3 2.1.6.3 Fire / Explosion - Section 2.4 2.1.6.4 Personnel Injury - Section 2.5 2.1.6.5 Natural Event - Section 2.6 2.2 For Initiating Event: Airborne Release 2.2.1 Radiation Protection Manager or designee direct a Dose Assessment Staff Member to initiate and continue offsite dose projection activities as neces'sary in accordance with SP 69.922 91, Determination of Offsite Doses.
2.2.2 Radiatior. Protection Manager or de"ignee call the OSC Supervisor for manpower in order to initiate an emergency onsite radiation survey in accordance with SP 69 921 91, onsite Surveys.
2.2.3 If the results of the onsite survey indicate the need, Radiation Manager or designee initiate radiation surveys offsite in accordance with SP 69 929.91, Downwind Surveys, and escalate the emergency classification as warranted.
2.2.4 Based on the results of the downwind dose projection activities, 1[
Radiation Protection Manager or designee recommend an appropriate protective action to offsite authorities as part of the initial s
and/or follow up notifications. Refer to SP 69.926 91, Protective Action Recommendations".
l 2.2.5 If the results of the radiation surveys or if area radiation maaitors indicate the need, Emergency Director or designee,
)
evacuate personnel from affected areas by implementing SP69.939.91, l
Evacuations During an Emergency, provides guidance as to when an i
evacuation should be implemented.
If an evacuation is implemented, also perform as applicable:
2.2.5.1 Emergency Director or designee account for personnel by implementing SP 69 939 92, Personnel Accountability.
i 2.2.5.2 Radiation Protection Manager or designee, direct Personnel monitoring efforts in accordance with SP69 939.93, Monitoring of Personnel / Equipment During an Evacuation.
~
2.2.5.3 Radiation Protection Manager or designee, direct search
<1 and rescue efforts in accordance with SP 69 989 91, Search and Rescue.
SP 69 914 01 Rev. I 7/09/82 Page 2
_. _. _ _ ~ _.. _ - _
2.2.5.4 Radiction Protsetion Mansgar or d2cignso, dincet rz-Ontry efforts in accordance with SP 69,070 01, Re-antry.
2.2.6 If the rectics of downwind surveys at the site boundary indicates a
(
dose rate exceeding 50 mr/hr for 1/2 hour or greater than 500 mr/hr whole body for two minutes (or five times these levels to the thyroid), Emergency Director, reclassify the emergency as a Site Area Emergency and pcrform emergency measures in accordance with SP 69 015 01, Site Area Emergency.
Immediately notify offsite authorities of the reclassification of the emergency.
2.3 Fpy Initiating Evert: Waterborne Release C1 2.3.1 In-plant Radiation Mo.nitoring Technician, determine the activity of the release by effluent monitor reading, nr by estimato in accordance with appropriate station procedures.
2.3.2 Radiation Protection Mana'ger or designee, direct Inplant Radiation Monitoring Technician to implement SP 69.024 01, Waterborne Release Dose Projection.
2.3.3 Radiation Protection Manager or designee, direct Dose Assessment Staff members to implement SP 69 026 01, Protective Action Recommendations.
2.4 For Initiating Event: Fire / Explosion 2.4.1 Control Room Operator, upon report of a fire or valid alarm direct
(
fire brigade memberc to perform fire fighting efforts in controlled areas in accordance with the SNPS Fire Plan.
t 2.5 For Initiating Event: Personnel Injury 2.5.1 Control Room Operator, upon receipt of a report of injury / illness implement SP 69.040 01, Personnel Injury or if the missing individuals location is not known implement SP 69 080 01, Search and Rescue.
2.6 For Initiating Event: Natural Event 2.6.1 Operations personnel perform emergency measures in accordance with (1
SP 29 001 01, Acts of Nature.
3.0 SUBSEQUENT ACTIONS 3.1 Emergency Director, direct a Communicator to fill out a Dose Assessment Fact Sheet (Appendix 12.2 of SP 69 009 01, Notifications) known using the most current data available at the time the form is completed.
3.2 When offsite agencies call back, Communicator provide information from the Approved Dose Assessment Fact Sheet as applicable to the emergency condition.
Accept calls and provide information to only those organizationt listed on the notification call-lists.
Refer all other calls
(
SP 69 014 01 Rev. 1 7/09/82 Page 3
to LILCO public cffairs par.sonnal.
- 3. 3' Ecergency Director, coordinate emergency response activities in the LILCO
<1 emergency response facilities keeping all LILCO support personnel apprised
(
of the emergency situation.
i 3.4 Emergency response personnel perform emergency measures in accord'adce with the appropriate Emergency Plan. Implementing Procedures (SP 69.XXX.XX l
series) and Emergency Operating Procedures (SP 29.XXX.XX series).
r 3.5 If plant conditions deteriorate, Emergency Director escalate the emergency
{
classification.
Perform actions in accordance with the SP 69 910 01, Classification of Emergency Action Levels.
(1 i i
3.6 Emergency Response personnel continue emergency eperncions, including l
assessment activities, until such time as plant conditions have stabilized
)
and other termination criteria of CIP-10, Recovery have been satisfied.
4.0 FINAL CONDITIONS 4.1 Emergency measures are continuing for the Alert, the emergency condition i
has been escalated / downgraded, or the emergency condition has been te rminated.
5.0 DISCUSSION i
[
5.1 Once an Alert condition has been declared at SNPS in accordance with SP 69 010.01, Classification of Emergency Action Levels, this procedure guides j
the Emergency Director in the performance of major actions and provides reference to other applicable Eastgency Plan Implementing Procedures for
(
further actions and more detailed instructions.
5.2 Although this procedure assigns all responsibility to the Emergency Director, the various activities will be performed by the it.dividual j
emergency managers.
Initially, and ut til the TSC staf fing is available, the Emergency Director will direct all functions performed by the on shif t compliment.
As the staffing arrives, che individual emergency managers will be responsible for performing activities assigned in SP 69 091 91, Emergency Organizations.
The Emergency Director will coordinate the
[
overall response using this procedure as a guide.
5.3 In the event of emergency conditions not adequately covered by this i
procedure, the Emergency Dire: tor has the responsibility and authority to take whatever action he considers required to aprevent injury to personnel or damage to the plant or to equipment and to place the plant in a safe condition.
6.0 APPENDICES N/A l
'(
SP 69 914.01 Rev. 1 7/09/82 Page 4 L
, - 9 bdb~l Submitted:
SP Number: 69.015.01 I
Reviewed /0Q ngr.:
zwp Revision:
1 Approved / Plant Mgr.:
Date Eff.:
7/09/82
/
SITE AREA EMERGENCY 1.0 CONDITIONS 1.1 A SITE AREA EMERGENCY has been declared based on the occurrence of events which involve actual or likely failures of plant functions needed for the protection of the public, as described in SF 69.010.01, Classification of Emergency Action Levels.
2.0 ID1EDIATE ACTIONS 2.1 For All Initiating Events 2.1.1 Control Room Operator, imple=ent corrective actions to contend with the situation and to citigate possible deterioration in plant conditions in accordance with the SNPS Operating Procedures while s1=ultaneously implementing this procedure.
<1 2.1.2 Control Rooo Operator, announce over the page/ party system the following:
2.1.2.1 The plant is in a SITE AREA ENERGENCY condition - Repeat 2.1.2.2 The location or general area affected 2.1. 2. 3 Any operations / work to be halted 2.1.2.4 Specific instructions to plant personnel as applicable 2.1.3 E=ergency Director / Response Manager, direct a communicator to fill cut a Notification Fact Sheet (Appendix 12.1 of SP69.009 01, 1
Notifications) using data derived from the initial assessment activities.
2.1.4 Coccunicator, i=ple ent SP 69.009 01, " Notifications" after receiving the approved Fact Sheet from the Emergency 1
Director / Response Manager in order to:
2.1.4.1 Notify offsite agencies 2.1.4.2 I!otify additional station emergency response personnel as needed 2.1.4.3 Notify the LILCO of fsite emergency response organization
.e,.-
,e
,_n.
-..,,,e,,,,.,,,.,_..m-..g,,
m.,
e
2.1.5 Emergency Director notify the Shif t Security Supervisor to:
<1 I
2.1.5.1 Imp 1'ement SP9X.XXX.XX, OSC Access Control 2.1.5.2 Implement SP9X.XXX.XX, TSC Access control 2.1.6 Emergency Director, based upon evacuation guidelines contained in SP69.030 01 Evacuations During an E=ergency, implement the following as necessary:
2.1. 6.1 SP 69 030.01, Evacuations During an Emergency 2.1.6.2 SP 69.030.02, Personnel Accountability 2.1.6.3 SP 69 030 03, Contamination control During Emergencies 2.1.6.4 If personnel are found to be tissing f rom accountability Emergency Director or designee implement SP 69 080.01, Search and Rescue.
2.1.7 Radiation Protection Manager or designee, direct Health Physics personnel to perform radiation and airborne radioactivity surveys at the designated assembly areas.
If the results of the radiation surveys at the primary assembly areas indicate radiation levels in excess of 10 mres/hr or gross airborne radioactivity (less noble gases) in excess of IE-9 uCi/ce, or if continued occupancy is expected to result in excess of 40 MPC-hours for the isotopic mix
(
less noble gases, relocate to another assembly area, or if evacuation guidelines exist, infor= the Icergency Diretor to
<1 implement a site evacuation in accordance with SP 69.030.01, Evacuations During an Emergency.
2.1.8 Perform any of the following as necessary:
2.1. 8.1 Airborne Release - Section 2.2 2.1.8.2 Waterborne Release - Section 2. 3 i
2.1.8.3 Fire / Explosion - Section 2.4 I
2.1.8.4 Personnel Injury - Section 2.5 2.1.8.5 Natural Event - Section 2.6
- 2. 2 For Initiating Event:
Airborne Release 2.2.1 Radiation Protection Manager or designee direct a Dose Assessment Staff Member to initiate and continue offsite dose irojection activities as necessary in accordance with SP 69 022 01, Determination of Offsite Doses.
k SP 69 015 01 Rev. 1 7/09/82 Page 2
4 2.2.2 Radiation Protection Manager or designee call the OSC Supervisor fl for manpower in order to initiate an emergency onsite radiation survey in accordance with SP 69.021.01, Onsite Surveys.
(
2.2.3 Radiation Protection Manager or designee call the OSC Supervisor kl for manpower in order to initiate radiation surveys offsite in accordance with SP 69.020.01, Downwind Surveys, and escalate the emergency classification as warranted.
2.2.4 Based on the results of the downwind dose projection activities, Radiation Protection Manager or designee recom:end an appropriate protective action to offsite authorities as part of the initial and/or subsequent follow-up notifications.
Refer to SP 69.026 01, Protective Action Recom=endations.
2.2.5 If the results of the downwind survey indicate a dose rate at the site boundary (not the protected area fence) exceeding 1 rem /hr W.B or 5 ren/hr thyroid, E=ergency Director reclassify the emergency as (1
a General Emergency and perform emergency measures in accordance with SP 69 016.01, General Emergency.
Immediately notify offsite authorities of the reclassification of the emergency.
2.3 For Initiating Event: Waterborne Release 2.3.1 Liquid releases are not identified as initiating significant events (1
for a Site Area Emergency since it is unlikely to have offsite doses in excess of EPA Protective Action Guides due to the release.
A liquid release could occur, however, concurrent with the events which initiated the Site Area Emergency.
Corrective and assessment
(
ceasures for liquid releases are provided in Section 2.3 of SP 69.014.01, Alert.
1 2.4 For Initiating Event:
Fire / Explosion 2.4.1 Control Room Operator, upon receipt of a report of a fire or valid
<1 alarm direct fire brigade cembers to perform firefighting ef forts in accordance with the SNPS Fire Plan.
2.5 For Initiating Event:
Personnel Injury 2.5.1 Control Room Operator, upon receipt of a report of injury / illness impleaent SP69.040.01, Personnel Injury or if a cissing individuals location is not known imple:ent SP69 080 01, Search and Rescue.
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2.6 For Initiating Event:
Natural Event 2.6.1 Operations personnel perforn emergency measures in accordance with SP29.031 01, Acts of Nature.
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SP 69.013 01 Rev. 1 l
7/09/82 Page 3 l
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f 3.0 SUBSEQUENT ACTIONS j
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3.1 Emergency Director / Response Manager direct a Communicator to fill out a di Dose Assessment Fact Shect (Appendix 12.2 of SP69.009.01, Notifications) using the most current data available at the time the form is completed.
3.2 When offsite agencies call back, Com=unicator provide information from the approved Dose Assessment Fact Sheet as applicable to the emergency condition. Accept calls and provide information to only those organizations listed on the notification call-lists.
Refer all other calls to LILCO public affairs personnel.'
I 3.3 E=ergency Director / Response Manager, periodically disseminate information on the status of the onsite operations and conditions to the offsite authorities and to LILCO emergency response facilities.
In particular:
l 3.3.1 Notify offsite authorities of any significant (>100 mrem) change in l
dose projections, or other significant changes in plant status.
i J
3.3.2 Provide a situation report (once an hour) to the Emergency 8
Operations Facility.
t l
j 3.4 Emergency Director / Response Manager coordinate emergency response
[
activities in the LILCO emergency response facilities, keeping all LILCO support personnel apprised of the emergency situation.
3.5 Emergency response personnel, perform emergency measures in accordance with l
,k-the appropriate Emergency Plan Implementing Procedures (SP69.XXX.XX series) and Emergency. Operating. Procedures (SP29.XXX.XX series).
3.6 If plant conditions deteriorate, Emergency Director / Response Manager shall reclassify the emergency in accordance with SP 69 010 01, _ Classification of
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Emer2_ency Action Levels.
3.7 Emergency response personnel continue emergency operations, including i
assessment activities, until such time as plant conditions have stablilized 6
and other termination criteria of CIP-10, Recovery.
4.0 FINAL CONDITIONS l-t 4.1 Emergency measures are continuing for the Site Area Emergency, the
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emergency condition has been escalated / downgraded, or the emergency condition has been terminated.
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5.0 EISCUSSION i
5.1 Once a Site Area Emergency condition has been declared at SNPS in accordance with SP 69.010.01, Classification of E:-wgency Action Levels, l
this procedure guides the Emergency Director in the performance of major I
i actions and provides reference to other applicable Emergency Plan Implementing Procedures for further actions and more detailed instructions.
Il l
i SP 69 015.01 Rev. 1 7/09/82 Page 4 i
.m,.
_ _, _- ~ _ _., -, -.. _ - _, _ -, _ _,.
5.2 Although this procedure assigns all responsibility to the Emergency Director, the various activities will be performed by the individual
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emergency managers.
Initially, and until the TSC staffing is available, the Emergency Director will perform all functions.
As the staffing arrives, the individual emergency managers will be responsible for performing activities assigned in CIP-21, Emergency Organizations.
<]
The Emergency Director will coordinate the overall response, using this procedure as a guide.
5.3 The Emergency Director / Response Manager is the only individual authorized
$1 to determine and recommend a protective action to offsite ' authorities (directly or via Communications Coordinator).
Therefore, the Emergency Director / Response Manager shall approve all initial and follow-up (I
notification messages for Site Area Emergency and General Emergency.
5.4 In the event of emergency conditions not adequately covered by this procedure, the Emergency Director / Response Manager has the responsibility 1
and authority to take whatever action he considers appropriate to prevent injury to personnel or damage to the plant or to equipment and to place the plant in a safe condition.
6.0 APPENDICES 6.1 N/A (1
]
t l
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SP 69 015.01 Rev. I 7/09/82 Page 5
- ttachment 4 - 10 Submitted
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4A SP Number 69.016.01 Revlewed/0QA ngr.:
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w Revision:.
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Approved / Plant Mgr.:
Date Eff.: 7 / 09'82 V
CENERAL EMERCENCY 1.0 CONDITION j
1.1 A GENERAL EdERCENCY has been declared based on the occurrence of events which involve actual or imminent substantial core degradation or melting with potential for loss of contain=ent integrity, as described in SP 69 010.01, Classification of Emergency Action Levels.
2.0 USEDIATE ACTIONS 2.1 For All Initiating Events 2.1.1 Control Room Operator imple=ent corrective actions to contend with the situation and to mitigate possible deterioration in plant conditions in accordance with Operating Procedures while simultaneously implementing this procedure.
2.1.2 Control Room Operator, announce over the page/ party system the following:
2.1.2.1 The plant is in a GENERAL EdERGENCY condition - repeat.
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2.1.2.2 The location or general area affected.
2.1.2.3 Any operations / work to be halted.
2.1.2.4 Specific instructions to plant personnel as applicable.
2.1.3 Emergency Director / Response Manager, direct a Communicator to fill out a Notification Fact Sheet (Appendix 12.1 of SP 69.009.01, Notifications), using data derived from the initial assessment activities.
NOTE:
Radiation Protection Manager or Designee, using the predetermined Protective Action Recommendations for General Emergency Classifications, (Appendix 6.1), notify the Emergency Director / Response >bnager of the protective action and notify offsite authorities in accordance with SP 69 009.01, Notifications.
2.1.4 Emergency Director / Response Manager, implement SP 69.039.01, Notifications in order to:
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2.1.4.1 Notify offsite agencies 2.1.4.2 Notify additional station emergency response personnel,as needed
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2.1.4.3 Notify the LILCO cf fsite emergency response organization 2.1.3 E=ergency Director notify the Shif t Security Supervisor to:
2.1.5.1 Implement SP 9x.xxx.xx, OSC Access Control.
2.1.5.2 Implement SP 9x.xxx.xx, TSC Access Control.
2.1.6 Emergency Director, based upon evacuation guidelines contained in SP 69.030.01 Evacuations During an Emergency, implement the following as necessary:
2.1.6.1 SP 69.030 01, Evacuations During an Emergency 2.1.6.2 SP 69.030 02, Personnel Accountability 2.1.6.3 SP 69 030 03, Contamination Control During E=ergencies 2.1.6.4 If personnel are found to be missing from accountability Emergency Director or designee implement SP 69.080.01, Search and Rescue.
2.1.7 Radiation Protection Manager or designee, direct Health Physics personnel to perform radiation and airborne radioactivity surveys at the designated assembly areas. If the results of the radiation I
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surveys at the primary assembly areas indicate radiation levels ta excess of 10 crem/hr or gross airborne radioactivity (less noble l
gases) in excess of 10 mres/hr or gross airborne radioactivity (less noble gases) in excess of IE-9 Ci/ce, or if continued occupancy is expected to result in excess of 40 MPC-hours for the isotopic mix less noble gases, relocate to another assembly area, or if evacuation guidelines exist, inform the Emergency Director to implement a Site Evacuation in accordance with SP 59 030.01, Evacuations During an Emergency.
2.1.8 Perform any of the following as necessary:
2.1.8.1 Airborne Release - Section 2.2 2.1.8.2 Waterborne Release - Section 2.3 2.1.8.3 Fire /Expolsion - Section 2.4 2.1.8.4 Personnel Injury - Section 2.5 2.1.8.5 Natural Event - Section 2.6 SP 69 016 01 Rev. 9
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7/09/82 Page 2 l
,, - - -.- ----.-, - - - - - - - - - - - - - ~ - - - ~ - - ' ' ~ - " ' ' ~ ~ ~ ~~~~~~~~~
2.2 For Initiating Event: Airborne Release 2.2.1 Radiation Protection Manager or Designee, direct a Dose Assessment
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Staff Member to initiate and continue offsite dose projection activities as necessary in accordance with SP 69.022.01, Determination of Offsite Doses.
2.2.2.
Radiation Protection Manager or Designee, call the OSC Supervisor for =anpower in order to initiate an emergency onsite radiation survey in accordance with SP 69.021 01, Onsite Surveys.
2.2.3 Radiation Protection Manager or Designee, call the OSC Supervisor for =anpower in order to initiate radiation surveys offsite in accordance with SP 69 020 01, Downwind Surveys.
2.3 For Initiating Event: Waterborne Release 2.3.1 Liquid releases are not identified as initiating significant events for a General E=ergency since it is unlikely to have offsite doses in excess of EPA Protective Action Guides due to the release.
A liquid release could cccur, however, concurrent with the events which initiated the General Emergency. Corrective and assessment measures for liquid releases are provided in Section 2.3 of SP 69 014 01, Alert.
2.4 For Initiating Event: Fire / Explosion 2.4.1 Control Room Operator, upon receipt of a. report of a fire or valid alarm direct fire brigade members perform firefighting efforts in
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accordance with the SNPS Fire Plan.
2.5 For Initiating Event: Personnel Injury 2.5.1 Control Room Operator, upon receipt of a report of injury / illness implement SP 69.040.01, Personnel Injury or if a missing individual's location is not known, implement SP 69 080.01, Search and Rescue.
2.6 For Initiating Event: Natural Event 2.6.1 Operations personnel perform emergency measures in accordance with SP 29 001 01, Acts of Nature 3.0 5"35EQUENT ACTIONS 3.1 Emorgency Director / Response Manager direct a Communicator to fill out a Dose Assessment Fact Sheet (Appendix 12.2 of SP 69 009.01, Notifications) using the most current data available at the time the form is completed.
3.2 Uhen cffsite agencies call back, Communicator provide information from the approved Dose Assessment Fact Sheet as applicable to the emergency condition.
Accept calls and provide infor=ation to only those
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SP 69.016.01 Rev. 0 7/09/82 Page 3
l l
i organizations listed on the notification call-lists. Refer all other calls to LILCO public aff airs personnel.
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3.3 Emergency Director / Response Manager, periodially disseminate information on the status of the onsite operations and conditions to the offsite l
authorities and to LILCO emergency response facilities.
In particular:
I 3.3.1 Notify offsite authorities of any significant (>100 mrem) change in dose projections, or other significant changes in plant status.
3.3.2 Provide a situation report (one an hour) to the Emergency Operations Facility.
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3.4 E=ergency Director / Response Manager, coordinate emergency response activities in the LILCO emergency response facilities, keeping all LILCO support personnel apprised of the emergency situation.
3.5 Emergency response personnel, perform emergency measures in accordance with the appropriate Foergency Plan Implementing Procedures (SP 69.rxx.xx series) and Emerdency Operating Procedures (SP 29.xxx.xx series).
3.6 Emergency response personnel continue emergency operations, including assessment activities, until such time as plant conditions have stabilized and other termination criteria of CIP-10, Recovery have been satisfied.
I 4.0 FINAL CONDITIONS 4.1 E=ergency measures are continuing for the General Emergency, the emergency condition has been downgraded, or the emergency condition has been
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t e r=ina te d.
5.0 DISCUSSION 5.1 Once a General Emergency condition has been declared at SNPS in accordance with SP 69.010.01, Classification of E=ergency Action Levels, this procedure guides the E=ergency Director in ene performance of major actions and provides reference to other applicable Emergency Plan Implementing Procedures for further actions and more detailed instructions.
5.2 Although this procedure assigns all responsibility to the Response Manager /
Emergency Df tector, the various activities will be performed by the l
individual Emergency Managers. Initially, and until the TSC staffing is available, the Emergene Director will perform all functions. As the staf fing arrives, the individual emergency managers will be responsible for performing activities assigned in CIP-21, Emergency Organization. The Emergency Director / Response Manager will coordinate the overall response, using this procedure as a guide.
5.3 The Response Manager / Emergency Director are the only individuals authorized to determine and recommend a protective action to of.fsite authorities (directly or via Communications Coordinator). Therefore, the Emergency / Director /Respcase Manager shall approve all initial and follow-up
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SP 69.016.01 Rev. 0 7/09/82 Page 4 i
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1 I
I notification messages for all emergency classifications.
5.4 In the event of emergency conditions not adequately covered by this
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procedure, the Response Manager /E=ergency Director has the responsibility and authority to take whatever action he considers appropriate to prevent injury to personnel or damage to the plant or to equipment and to place the plant in a safe condition.
6.0 APPENDICES I
- 6. l' Predeter=ined Protective Action Reco=mendations for General Emergency j
Classifications.
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i i
l i
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I 1
SP 69 016 01 Re i. 0 7/09/82 Page 5 2
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1 PREDETERMINED PROTECTIVE ACTION
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r RECOMMENDATlONS FOR-GENERAL EMERGENCY CLASSIFICATIONS 1
2 CORE CO N TAIN MENT PAR TO BE FAILURE F AI LUR E CONSIDERED
,A.
COND.
NO NO (l
] 2 MILES I
'v' D E TION
/[;
COND.
YES NO
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12 f
E
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5 MILES WIND DIRECTION LIKELY BUT r
'~
COND.
YES NOT WITHIN III 3 HOURS 10 MILES WIN D DIRECTION CO D.
YES WITHI 3 HOURS 5
l0 NOTE:
- 1. CORE FAILURE-RELEASE OF FISSION PRODUCTS INTO CONTAINMENT
- 2. CONTAINMENT FAILURE-RELEASE OF FISSION PRODUCTS INTO ATMOSPHERE
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AREA AREA DI E ON TOWARD SF 69 916.91 Rev. 9 7/09/82 Page 6 1
~ ~.
PROTECTIVE ACTIUN RECGMMENDATIONS D^RPA FOR GENERAL' CLASSIFICATION
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i (DEGREESI CON 0! TION I CONDIT10N II CONDITION III CONDIT10N IV 348 TO EVACUATE: ABCDEFGH1 EVACUATE: ABCDEFGillJ SHELTER: ABCDEFGHIJ N
NM E : D N.
gg SHELIER:
J KLMNORS KLMNORS 1
11 TO EVACUATE: ABCDEFGHI EVACUATE: ABCDEFGHIJ SHELTER: ADCOEFGHIJ Nt EVACUATE: ABCDE j
34 SilE L T E R :
J KLMNOUR KLMN00R 34 TO EVACUATE: ABCDEFGH EVACUATE: ABCDEFGHIJ SHELTER: ABCDEFGHlJ NE
"^
' ^
56 SHELTER:
IJ KLMNOR KLMNOR SG TO EVACUATE: ABCDEf Gil EVACUATE: A000EFGHIJ SHELTER: ABCDEFGHIJ ENE EVACUATE: AtlCOE 79 SHELTER:
IJ KLMOR KLMOR 79 TO EVACUATE: ABCDEFG EVACUATE: ABCDEFGHIJ SHELTER: ABCDEFGHIJ E
101 SilEL T E R :
HIJ KLOR KLOR 101 TO EVACUATE: ABCDE ESE 124 SHELTER:
HIJ K0 4
124 TO EVACUATE: ABCDE SE 146 SHELTER:
GHIJ 46 TO EVACUATE: ABCDEF EVACUATE: ABCDEFGHlJ SHELTER: ABCDEFGHIJ l69 j
SSE SHELTER:
GHIJ l
169 TO EVACUATE: ABCDEF EVACUATE: ABCDEFGHIJ SHELTER: ABCDEFGHIJ S
EVACUATE: ABCDE 191 SHELTER:
GHIJ 19I EVACUATE: ABCDEF EVACUATE: ABCDEFGHIJ SHELTER: ADCDEFGHIJ SSH EVACUATE: AOCDE 214 SHELTER:
GHIJ 4 TO EVACUATE: AOCOEFJ EVACUATE: ABCDEFGHIJ SHELTER: ABCDEFGHIJ EVACUATE: ABCDE SW 236 SHELTER:
GH1 P
P 236 TO HSW EVACUATE: ABCDE 258 SHELTER:
GH O
O 250 TO y
EVACUATE: ABCDE j
281 SHELTER:
GH 0
O TO EVACUATE: ABCDEFHIJ EVACUATE: ABCDEFGHIJ SHELTER: ABCDEFGHIJ NNW EVACUATE: ABCDE SHELTER:
G NOS NOS 303 TO EVACUATE: ABCOEFGHIJ EVACUATE: ABCDEFGHIJ SHELTER: ABCDEFGHIJ NW EVACUATE: ABCDE 326 SHELTER:
MNOS MNOS 326 TO EVACUATE: ABCDEFGHIJ EVACUATE: ABCDEFGHIJ SHELTER: ABCDEFGHIJ g
EVACUATE: ABCDE 348 SHELTER:
LR LR a
iP 69.916 91 Rev. $
I 7/09/82 Page 7 g,,,, g i
St.bmf ttsd:
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Approved / Plant Mgr.:
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SP Number 69.022.01 Revision: e i
Date Eff.: 7/no/g; l
TPC l
TPC TPC DETERMINATION OF OFFSITE DOSES I
1.0 PURPOSE The purpose of this procedure is describe the method to determine offsite doses.
2.0 RESPONSIBILITY The Radiation Protection Manager / Radiological Control Manager shall be responsible for the implementation of this procedure.
PPF 1021.600-6.421
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3.0 DISCUSSION 3.1 This procedure is used to determine offsite doses based upon short term, abnormal release conditions. The dose calculations are based upon finite
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cloud analyses.
3.2 There are two methods described in this procedure. One makes use of the computerized radiation monitoring system (RMS), while the other. is a manual method to be used in cases of RMS unavailability.
3.3 The computerized RMS method described in the" procedure assumes that the software is running in the ACCIDENT mode. This mode is selected either manually or automatically by the RMS.
It is important to note that initial dose assessment, prior to grab sample analyses, is based upon an assumed inventory mixture of nuclides (i.e. LOCA, fuel handling). '
3.4 The manual method described in this procedure employs the use of nomograms for dose assessment. There are eight (8) nomograms from which to select.
l Each nomogram is based upon assumed LOCA nuclide release mixtures.
When j
using this method, it is important to understand the bases and assumptions l
described on each nomogram.
3.4.1 Only whole body dose calculations are provided for the normal station ventilation exhaust monitor. These doses assume 100% noble gas LOCA mixtures.
l 3.4.2 Both whole body and thyroid dose calculations are provided for the l
reactor building standby ventilation system monitor.
These doses assume 100% noble gas LOCA mixtures for the whole body, and 25%
halogen LOCA mixtures with 99% filtration for thyroid doses.
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3.5 This procedure details the method to obtain dose projection for o'ne point from beginning to end. The Radiation Protection Manager / Radiological Control Manager can have several different people doing this calculation for different distances simultaneously.
If this is the case, the worksheet (Appendiz 12.1) is filled out until the atmospheric dispersion factor (item
- 13) is obtained. Once this is done the highest dose can be obtained by using the nomograms for situations where time limits are constrained. The RPM /RCM will use the best method for completing this procedure depending on staff availability.
3.6 Topics covered in this proc'edure:
Jha ga j
8.1 Determination of offsite doses using the 3
comuterized radiation monitoring system
- 8. 2 Determination of offsite doses using the 3
nomograms Appendix 12.1 Radioactive Ef fluent Monitor Nomogram Worksheet Appendix 12.2 Tabulated Dose and Protective Action Worksheet Appendix 12.3 Terrain Heights SF 69.622.01 Rev. 9
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7/09/82 Page 2
App;ndix 12.4 Plume Canterlina Concsntratica (Xu/Q)
AppIndix 12.5 Gauncien Puff Gamma (Xu/Q)
Appendix 12.6 Nomograms
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4.0 PRECAUTIONS N/A 5.0 PREREQUISITES N/A 6.0 LIMITATIONS AND ACTIONS 6.1 Personnel using this procedute should be aware of the bases for the assumed nuclide mixtures used in the dose calculations.
7.0 MATERIALS AND EQUIPMENT 7.1 Radiation Monitoring System 8.0 PROCEDURE 8.1 Determination of offsite doses using the computerized radiation monitoring system.
(RMS)
(LATER)
- 8. 2 Determination of offsite doses using the nomograms.
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8.2.1 Dose Assessment Staff Members or In plant Radiation Monitoring Technician, obtain a copy of the Radioactive Effluent Monitor Nomogram Worksheet (Appendix 12.1) and fill out the worksheet using the following instructions:
d.2.1.1 Record the current date (item 1) and time (iten 2) 8.2.1.2 Obtain wind speed (item 3) and wind direction (item 4) for both 150 ft. and 33 ft. tower levels from either the Control Room or local tower readouts. Convert wind speed to approp,riate units.
Determine affected downwind sector (item '4) by referring to the following table:
Indicated Wind Direction Affected Downwind Se'etor 0 to 11.25 S
11.25 to 33.75 SSW 33.75 to 56.25 SW 56.25 to 78.75 WSW 78.75 to 101.25 W
101.25 to 123.75 WNW 123.75 to 146.25 NW 146.25 to 168.75 NNW 168.75 to 191.25 N
191.25 to 213.75 NNE 213.75 to 236.25 NE
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236.25 to 258.75 ENE SP 69.022.01 Rev. 9 7/09/82 Page 3
Indientsd Wind Diraction Affsetsd Downwind Ssetor 258.75 to 281.25 E
281.25 to 303.75 ESE
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303.75 to 326.25 SE 326.25 to 348.75 SSE 348.75 tb 371.25 S
371.25 to 393.75 SSW 393.75 to 416.25 SW 416.25 to 438.75 WSW 438.75 to 461.25 W
461.25 to 483.75 WNW 483.75 to 506.25 NW 506.25 to 528.75 NNW 528.75 to 540.00 N
8.2.1.3 Determine atmospheric stability class (item 5a, b, or c) using one of the following methods:
.1 Obtain the 33-150 ft. temperature difference (item Sa) from the Control Room or local tower readout.
Choose the correct stability class from the following table:
Delta-T (*F)
Stability Atmospheric 33-150 ft Class Condition Less than -1.22 A
Extremely Unstable
-1.22 to
-1.09 B
Moderately Unstable
-1.09 to
-0.96 C
Slightly Unstable
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-0.96 to 0.32 D
Neutral 0.32 to 0.96 E
Slightly Stable 0.96 to 2.57 F
Moderately Stable Greater than 2.57 G
Extremely Stable NOTE:
For borderline cases, choose the most stable class (e.g.,
if delta-T = 0.32, choose stability Class E).
.2 If the temperature difference (item Sa) is not available, record the standard deviation of wind direction fluctuation (sigma theta - item 5b) from either the 33-ft. lerel of the primary tower or the bsekup tower, and choose the correct stability class from the following list:
sigma theta (degrees)
Stability Atmospheric 33-ft. Level Class Condition creater than 22.5 A
Extremely Unstable 17.5 to 22.5 B
Moderately Unstable 12.5 to 17.5 C
Slightly Unstable
- 7. 5 to 12.5 D
Neutral 3.8 to 7.5 E
Slightly Stable 2.1 to 3.8 F
Moderately Stable Less than 2.1 G
Extremely Stable
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SP 69.922.91 Rev. 9 7/09/82 Page 4
NOTE: For bordarlina ecces, choose tha most stable clace (e.g., if sigma theta = 7. 5, choose stability Class E).
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.3 If no delta-T or sigma theta data is available, choose the stability class using the wind speed from e
item 3 and the following table:
33-ft Wind
' Day Night Speed Incoming Solar Radiation Degree or Cloudiness (aph)
Strong Moderate Slight >50%
<50%
l
<4 A
A-B B
4-7 A-B B
C E
F 7-11 B
B-C C
D
-E 11-14 C
C-D D
D D
>14 C
D D
D D
l The degree of cloudiness is defined as that fraction of the sky 1
above the local apparent horizon that is covered by clouds.
The j
neutral Class D, should be assumed for heavy overcast conditions during day or night.
i NOTE:
For borderline windspeed, choose the most stable class (e.g. if windspeed = 11 aph, i
choose stability Class C for daytime with strong incoming solar radiation).
i 8.2.1.4 Determine the type of release (ground-level or elevated)
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by contacting the Control Room and obtaining,the station vent average flow rate (item 6a).
Calculate the exit velocity (item 6b) and the velocity ratio (item 6c).
Circle the release type (item 6d).
8.2.1.5 Radiation Protection Manager, Radiological Control Manager, or In plant Radiation Monitoring Technician, determine the distance to downwind receptor (item 7).
NOTE: Use judgement when picking valves at which to perform dose projection. Taka into account factors such as windspeed, stability class, affected areas, and population. density.
Dose projection can only be done for distances given in Appendix 12.3.
If dose assessment staff members are available, several calculations can be performed simultaneously at different distances.
If this is the case the Radioactive Effluent Monitor Nomogram Worksheet (Appendix 12.1) can be completed for these different distances up to item 13 (atmospheric dispersion factor) and recorded on the Tabulated Dose and Protective Action Worksheet (Appendix 12.2) before using the nomograms and completing the worksheets.
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1 SP 69 922 01 Rev. 9 7/09/82 Page 5
i 8.2.1.6 Determins receptor elsvation abova meen esa 1sval (MSL) l by using Appendix 12.3 along wit,h stability class (item
- 5) and distance to downwind receptor (item 7).,
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NOTE: THIS STEP FOR ELEVATED RELEASES ONLY.
8.2.1.7 Determine plume rise (item 9) for the appropr.iate stability class (item 5), and record the lowest valve using the guidance on the worksheet.
NOTE: THIS STEP FOR ELEVATED RELEASES ONLY 8.2.1.8 Calculate the effective plume height above receptor (item
- 10) and then choose the tabulated plume height closest to this value.
NOTE: THIS STEP FOR ELEVATED RELEASES ONLY 8.2.1.9 Contact the Control Room and determine the release point (item 11). Determine the type of exposure (item 12) by circling the system affected.
8.2.1.10 Determine the atmospheric dispersion factor for type of exposure (whole body gamma and/or thyroid) as follows:
.1 Select the gaussian puff gamma Xu/Q tables (Appendix 12.5) for whole body exposure or plume centerline concentration Xu/Q tables (Appendix 12.l.) for thyroid exposure.
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.2 From type of release (item 5) and/or tabulated plume height (item 10 - for elevated releases), choose the proper table for whole body and/or thyroid exposure.
l
.3 Find the proper Xu/Q value using the stability class (item 5) and distance to downwind receptor (item 7).
Record the Xu/Q value (item 13) on the worksheet.
i 8.2.1.11 Contact,the Control Room and determine the radiation j
monitor reading (item 14) in epm.
If the radiation monitor resding is offscale or inoperable obtain Xe-133 and I-131 dose equivalents from results of a grab sample.
l NOTE:
Inform RPM or RCM that a sample is needed if not already taken.
8.2.1.12 Based upon release point (" tem 11), type of exposure (item 12) and radiation monitor reading cr dose equivalents (item 14) determine the proper nomogram (s) to use.
Record the number (s) on the worksheet (item 15) and obtain a copy of the nomogram (Appendix 12.6).
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SP 69.022 91 Rev. 9 7/09/82 Page 6
s Nom: gram No.
Dercription 1
Station vent routine effluent monito r
. noble gas release
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. wholebody gamma dose 2
Station vent high-range monitor
. noble gas release
. wholabody gamma doce 3
RBSVS low-range monitor
. noble gas release
. wholebody gamma dose 4
RBSVS low-range monitor
. potential halogen release rate
. potential thyroid dose rate 5
. RBSVS intermediate-range monitor
. noble gas release
. wholebody gamma dose 6
RBSVS intermediate-range monitor
. potential halogen release rate potential thyroid dose 7
RESVS high-range monitor
. noble gas release
. wholabody gamma dose
(.
.4 8
RBSVS high-range monitor
. potential halogen release rate potential thyroid dose rate 8.2.1.13 Contact the Control Room to determine the airflow at the duct sampled or monitored (item 16) and time of reactor scram (item 17).
Determine time since reactor scram.
NOTE:
If the reactor is not yet shutdown, the time since reactor scram is zero.
8.2.1.14 Use the selected nomogram and the following information to compute the radioactivity release rate and the dose rate (item 18) at the receptor of interest:
. Monitor reading or grab sample concentration (from Step 14)
. Vent flow (from Step 16) j
. Time since reactor scram (from Step 17) j
. Prevailing wind speed (from Step 3 in mph; use the 33-f t data for a ground-level release and the 150-f t I
data for an elevated release as determined in Step 6)
. The Xu/Q value (from Step 13) 1
?
(
SP 69.922.91 Rev. 9 7/09/82 Page 7
8.2.1.15 To Datarminn Dosa Rate
.1 Locate the monitor reading on the lef t hand axis.
If monitor reading is unavailable, use grab sample
(
dose equivalent and continue with Step 8.2.14.4.
.2 Move horizontally to the right until the slanted line corresponding to the flow rate is intercepted.
.3 Move vertically up until slanted line corresponding to time after reactor shutdown is intercepted.
.4 Move horizontally to the right until slanted line corresponding to wind speed is intercepted.
NOTE: For elevated releases, use elevated windspeed; for ground releases, use ground win'dspeed.
.5 Move vertically down until the slanted line corresponding to the atmospheric dispersion factor is intercepted.
.6 Nove horizontally to the right and read off the dose rate.
8.2.1.16 To Determine Release Rate
.1 Locate the monitor reading on the left hand axis.
(
.2
' Move horizontally to the right until the slanted line corresponding to the flow rate is intercepted.
.3 Move vertically down until slanted line corresponding to time af ter reactor shutdown is intercepted.
.4 Move horizontally to the left and read off the release rate.
8.2.1.17 Contact the Control Room and determine release duration (item 19).
8.2.1.18 Complete item 20 to determine whole body and thyroid dose for the point of interest. Record them on Appendix 12.1.
9.0 ACCEPTANCE CRITERIA l
N/A I
(
l SP 69 922 91 Rev. 9 7/09/82 Page 8
I l
10.0 FINAL CONDITIONS Projected whole body and/or thyroid doses for points of interest have been calculated.
('
11.0 REFERENCIS Shoreham Nuclear Power Station Emergency Plan 12.0 APPENDICES 12.1 Radioactive Effluent Monitor Nomogram Worksheet, SPF69.022.01-1 12.2 Tabulated Dose and Protective Action Worksheet, SPF69.022 91-2 12.3 Tarrain Heights
- 12. 4 Plume Centerline Concentration Xu/Q 12.5 Gaussian Puff Ga=ma Xu/Q 12.6 Nomograms
(
l (
1 l
SP 69.022.01 Rev. 9 7/09/82 Page 9
_ _. _.,. _.. _.. _... ~. _ _ _ _ _. _ _
i i
-APPENDIX 12.1 i
Pcg2'l cf 4 RADI0 ACTIVE EFFLUENT MONITOR NOMOGRAM WORKSHEET j
Your Name:
f 1.
Date:
2.
Time:
3.
Wind speed:
u(33-ft level) aph; I 9.447 =
m/sec u(150-ft level) mph; X 9.447 =
m/sec i
l 4.
Wind direction: 33-ft level degrees; sector j
150-ft level degrees; sector,
t t
(See page 3 of procedure for affected downwind sector) t 5.
Atmospheric Stability (Pick one - use a, b, or e in that order.
See Step 8.2.1.3 for instructions).
a.
Delta Temperature: (33-150 ft) deg. F; stability
(
- b. Sigma Theta (33 ft)
- stability c.
Wind Speed (33 ft) aph; I
Time of Day (Choose one and circle appropriate condition in parenthesis) f Day Incoming Solar Radiation (Strong, Moderate, Slight) i Night Degree of Cloudiness (>50%, <50%)
l Stability
(
6.
Release Type
- E a.
Station vent flow: F cfm b.
Exit velocity
- Wo = F(cfm) I 8.47 X 10-5 =
m/sec Rv = Wo(m/sec) / u(150-f t; m/sec) =
I c.
Velocity ratio i
NOTE:
If Rv is less than.5, the release is to be ascumed to be at ground l
1evel; if Rv is greater than or equal to 5 the release is elevated.
{
d.
Release type (circle one): ground release elevated release 7.
Distance to downwind receptor:
X=
miles I
I NOTE: FOR GROUND RELEASE (item 6d) PROCEED DIRECTLY TO STEP 11 8.
Receptor elevation: ht=
m above MSL (ELEVATED RELEASE ONLY) from
~
Appendix 12.3; use stability class (item 5) and distance to downwind receptor (item 7).
t, SPF 69 922.91-1, Rev. 9 1
r I
i
(
b l
SP 69.922 91 Rev. 9 1
7/09/82 Page 10
. _ _ _., _ _ _.. _ _ L
AFPENDIX 12.1 Peg 2 2 of 4 9.
Plume rise:
(FOR ELEVATED RELEASES ONLY)
(
Compute hpr(1) and hpr(2) for all stabilities:
2 X)1/3 =
hpr(I) 32.4 (Rv
=
m hpr(2) 7.98 Rv
=
=
m Compute hpr(3) and hpr(4) for s;. ability classes E, F, and C only:
30 Wo /2 =
m (stability E) l hpr(3)
=
i 24 Wo /2 =
m (stability F) l
=
21 Wo /2,
l
=
,, (stability G) 6.4 (RvWo)I!
hpr(4) m (stability E)
=
=
5.5 (RvWo)l/3 =
m (stability F)
=
4.9 (RvWo)l/3 =
m (stability G)
=
Choose the final plume rise (hpr) as follows:
Stabilities A, B, C, and D hpr = lesser of hpr (1) and hpr (2) =
m k
Stabilities E, F, and G hpr = lesser of h r (1) through hpr (4) =
p m
10.
Effective plume height above receptor (FOR ELEVATED RELEASES ONLY). Use hpr (item 9) and he (item 8) 75.9 + hpr - he he
=
75.9 +
=
m Tabi21sted plume height (H) closest to he is:
H (choose 35, 70, 105 or 140) =
m 11.
Release point (circle one): Station Vent; RBSYS SPF69 022.01-1 Rev. 9 l
(
SP 69 922.91 Rev. 9 7/09/82 Page 11 t
j Appendix 12.1 l
Pega 3 cf 4 12.
Type of exposure (circle release point): whole body (station vent or RBSVS)
{
thyroid (RBSYS only) 13.
Atmospheric dispersion ^ factor Type of exposure (item 12):
Whole Body Use gaussian puff gamma Xu/Q ta51es (Appendix 12.3)
Thyroid Use plume centerline concentration Xu/Q tables (Appendix 12.4)
Type of Release:
(Ground or elevated.
If elevated release use tabulated plume height from item 10.
Use proper table for thyroid and/or whole body exposure).
Choose one:
ground level release elevated release (H = 35 m) elevated release (H = 70 m) elevated release (H = 105 m) elevated release (H = 140 m)
Stability and distance (item 5 and 7)
Find the proper Xu/Q value for whole body and/or thyroid exposure using stability class (item 5) and distance to downwind receptor (item.7).
(
Xu/Q (whole body) 2 (1/m )
=
Xu/Q (thyroid)
(1/m )
=
NOTE: Record these values and distance (item 7) on Appendix 12.2 14.
Radiation monitor reading:
cpm; Xe-133 Dose Eq.
uCi/cc l-131 Dose Eq.
uCi/cc 15.
Number of nomogram selected:
(Whole Body)
(Thyroid) 16.
Air flow at the duct sampled or monitored:
cfm 17.
Time of reactor scram:
- Time since reactor scram ~
hours (24 hr clock) 18.
a.
Radioactivity release rate:
uCi/sec; noble gas b.
Offsite dose rate:
ar/hr; whole body gamma c.
Radioactivity release rate:
u21/sec; radiciodine d.
Offsite dose rate:
ar/hr; thyroid l
SFF 69 922 91-1, Rev. 9
(
l SP 69 922 91 Rev. 9 7/09/82 Page 12
~
Appendix 12.1 Pegt 4 of 4 19.
Release duration:
hrs.
20a. Whole Body Dose Item 18b x item 19
=
=
x
/ 1000 =
rem b.
Thyroid Dose Item 18d x item 19
=
=
x
/ 1000 =
rea
(
SPF 69 922 91-1, Rev. 9
(
SP 69 922.91 Rev. 9 7/09/82 Page 13
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O APPENDIX.8 4
Paga 1 of.
SHOREHAM 8TATION - PLIK-CENTERLIE COEENTRATION (XeU/8) (1/M2) 4 I
GROUND-LEVEL RELEASE - DIVIDE RESILTS 8Y DE MILLION l
MILES A
8 C
D E
F G
.18 73.824 142.587 218.895 451.874 733.325 1528.773 3529.498
.25 40.552 83.988 155.855 307.503 517.294 1038.091 2177.300
.50 6.338 25.814 58.855 134.300 203.135 428.88f 348.132
.75 2.668 10.212 28.689 80.639 132.640 244.169 489.947 1.0 2.088 4.832 18.422 55.140 94.347 165.540 338.834 1.5 1.488 2.004 8.447 31.746 55.471 108.474 195.837 2.0 1.147 1.561 5.844 20.816 38.311 74.644 137.574 2.5
.945 1.295 4.019 14.791 28.672 57.294 106.706 3.0
.816 1.089 2.859 11.342 22.595 47.484 89.414 3.5
.720
.944 2.283 8.000 18.490 40.239 76.541 4.0
.644
.838 1.825 7.503 15.572 34.709 66.653 1
4.5
.585
.758 1.495 6.342 13.398 30.134 58.595 5.0
.536
.693 1.258 5.469 11.722 26.607 52.261 1
)
7.5
.368
.497
.713 3.206 7.151 17.112 34.340 I
10.0
.288
.390
.524 2.164 5.020 12.609 25.580 1
]
15.0
.214
.274
.360 1.204 3.036 8.008 16.872 l
20.0
.166
.215
.281
.811 2.185 5.881 12.691 1
25.0
.138
.17S
.245
.603 1.709 4.592 10.209 I
30.0
.120
.155
.213
.478 1.415 3.793 8.580 1
1 35.0
.106
.136
.188
.393 1.203 3.225 7.408 I
40.0
.096
.122
.168
.333 1.044 2.800 8.528
)
45.0
.087
.110
.148
.291
.827 2.482 5.853 l
50.0
.080
.100
.135
.258
.829 2.222 5.302 j
SP 69 922 91 Rev. g 7/09/82 p8Ee 16 4
1
^
^
i APPENDIX a.4 I Page 2 of 5 SHORDIAM 8TA110N - PLi#E-CENTERLIE CIN:ENTRATION (N#U/8) (1A12)
ELEVATED RELEASE (H = 35 M) - DIVIDE REStA.TS 8Y DE MILA.10N MILES A
8 C
D E
F G
.19 68.928 108.083
!!3.557 28.242 1.460
.000
.000
.25 39.738 81.890 109.985 58.158 12.023
.008
.000
.50 6.358 25.347 52.237 85.824 75.274 8.315
.021
.75 2.678 10.179 28.570 83.928 79.718 36.060 1.999 1.0 2.094 4.932 17.988 47.501 68.012 53.482 8.535 1.5 1.490 2.007 9.336 29.294 46.335 57.480 25.584 l
1 2.0 1.148 1.563 5.803 19.517 33.868 49.653 31.496 2.5
.945 1.296 4.000 14.188 26.067 42.113 34.222 3.0
.817 1.089 2.848 10.984 20.847 36.862 35.829 l
3.5
~
.720
.945 2.277 8.843 17.257 32.380 35.481 4.0
.644
.838 1.821 7.337 14.657 28.644 34.054 4.5
.585
.758 1.492 6.220 12.700 25.335 31.933 5.0
.536
.693 1.256 5.375 11.174 22.693 29.973 7.5
.368
.497
.713 3.169 8.917 15.173 23.013 10.0
.288
.380
.524 2.148 4.808 11.407 18.379 l
15.0
.214
.274
.360 1.197 2.976 7.488 12.914 20.0
.166
.215
.291
.808 2.149 5.495 10.097 25.0
.138
.179
.245
.601 1.685 4.338 8.305 30.0
.120
.155
.213
.476 1.397 3.601 7.063 35.0
.106
.136
.188
.392 1.189 3.073 6.159 40.0
.096
.122
.168
.332 1.033 2.878 5.470 45.0
.087
.110
.349
.291
.917 2.380 4.841 SP 69 922 9!
Rev. 9 50.0
.000
.100
.135
.257
.821 2.137 4.503 7/09/82 Page 17
r APPENDIX 12.4 '
Peg 2 3 cf 5 SHOREHAN STATION - PLIFE-CENTERLIE CDIENTRATION (XeU/8) (1/M2)
ELE')ATED RELEASE (H = 70 MI - DIVINE RESULTS SY DE MILLION d '.ES A
B C
D E
F G
.19 36.107 17.438 3.011
.000
.000 0.000 0.000
.25 28.850 29.170 12.598
.048
.000
.000 0.000
.50 6.220 20.704 27.534 7.216
.625
.000
.000
.75 2.678 8.557 20.869 15.801 5.276
.017
.000 1.0 2.094 4.811 14.825 18.538 10.678
.306
.000 1.5 1.490 2.005 8.453 17.158 15.615 2.668
.009 2.0 1.148 1.563 5.464 13.491 15.683 5.811
.065 2.5
.945 1.296 3.838 10.754 14.247 7.865
.218 3.0
.817 1.089 2.859 8.824 12.511 8.982
.548 3.5
.720
.945 2.223 7.383 11.092 9.448
.957 4.0
.644
.838 1.787 6.292 S.92S 9.519 1.366 4.5
.585
'.758 1.470 5.442 8.993 S.286 1.67S 5.0
.536
.693 1.240 4.774 8.187 8.978 1.956 7.5
.368
.497
.711 2.S28 5.563 7.417 2.955 10.0
.288
.390
.524 2.025 4.105 6.240 3.237 15.0
.214
.274
.360 1.155 2.611 4.668 3.058 20.0
.166
.215
.291
.786 1.930 3.687 2.878 25.0
.138
.179
.245
.588 1.535 3.046 2.639 30.0
.120
.155
.213
.468 1.283 2.600 2.382 35.0
.106
.136
.188
.386 1.100 2.272 2.181 40.0
.096
.122
.168
.328
.961 2.021 2.019 45.0
.087
.110
.149
.288
.857 1.829 1.891 50.0
.000
.100
.135
.255
.770 1.668 1.778 SP 69 922.91 Rev. 9 7/09/82 Page 18
^
APPENDIX 12..
Paga 4 of 5
,SHOREHAM STAT!!M - PLINE-CENTER 1.!E CINCENTRATI!Bt (XeU/8) (1/N2)
ELEVATED RELEASE IN = 105 M) - D1 HIDE RESULTS 81f DNE MILI.!ON MILES A
8 C
D E
F G
.18 12.281
.834
.007
.000
.000 0.000 0.000
.25 18.698 5.221
.340
.000
.000 0.000 0.000
.50 5.996 14.777 8.484
.118
,000
.000 0.000
.75 2.678 8.602 12.364 1.538
.057
.000
.000 1.0 2.094 4.617 10.730 3.864
.488
.000
.000 1.5 1.490 2.001 7.162 7.036 2.548
.016
.000 2.0 1.148 1.563 4.943 7.291 4.347
.163
.000 2.5
.945 1.296 3.583 6.768 5.205
.481
.000 3.0
.817 1.089 2.717 6.125 5.342
.B54
.001 3.5
.720
.945 2.137 5.464 5.310 1.213
.002 4.0
.644
.830 1.731 4.871 5.188 1.518
.006 4.5
.585
.758 1.432 4.355 5.059 1.743
.012 5.0-
.536
.653 1.215 3.919 4.876 1.915
.021 7.5
.368
.497
.707 2.566 3.869 2.250
.097 10.0
.288
.390
.523 1.B37 3.070 2.283
.179 15.0
.214
.274
.360 1.067 2.100 2.124
.277 20.0
.168
.215
.291
.752 1.814 1.896
.355 i
25.0
.138
.179
.245
.567 1.313 1.690
.390 30.0
.120
.155
.213
.454 1.115 1.511
.389 i
35.0
.106
.136
.188
.377
.967 1.374
.387 40.0
.096
.122
.168
.321
.852 1.264
.383 45.0
.097
.110
.148
.282
.765 1.179
.381 50.0
.000
.100
.135
.251
.691 1.104
.378 SP 69.922.$1 Rev. 9 7/09/82 Page 19
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APPENDIX
.5 Pagn I ci s SEOiAM 8TATI(M - GAUSSIAN PLFF GAPetA (M*U/81 (1/M21 GROUND-LEVEL RELEASE - DIVIDE RE8tLTS 8Y OfE N!!. LION MILE 8 A
8 C
D E
F G
.18 38.618 60.088 77.110 113.774 144.884 205.887 302.182
.25 28.073 48.380 83.374 82.861 121.875 171.481 242.415 l
.50 5.848 18.542 33.188 57.885 73.815 110.505 155.705
.75 1.285 8.628 20.853 42.003 57.528 81.865 118.788 1.0
.974 4.483 14.175 32.468 46.510 85.888 87.598 1.5
.697 1.597 8.063 21.733 32.608 50.222 72.387 2.0
.539
.788 5.250 15.523 25.008 38.811 58.816 2.5
.445
.608 3.716 11.828 20.109 33.347 50.281 3.0
.384
.512 2.785 8.448 18.884 28.220 44.929 3.5
.339
.444 2.174 7.787 14.217 25.826 40.582 4.0
.304
. 394 1.751 6.577 12.347 23.241 3S.890 4.5
.276
.357 1.439 5.655 10.886 20.889 33.869 5.0
.253
.327 1.209 4.841 8.718 18.882 31.273 7.5
.174
.235
.630 3.005 6.301 13.348 23.056 10.0
.136
.184
.400 2.065 4.968 10.342 18.410 15.0
.101
.128
.217 1.188 2.854 7.032 13.182 20.0
.078
.102
.151
.793 2.084 5.264 10.388 i
l 25.0
.065
.084
.116
.581 1.644 4.208 8.827 30.0
.057
.073
.101
.488 1.368 3.520 7.409 35.0
.050
.064
.089
.385 1.168 3.022 6.503 40.0
.045
.058
.078
.326 1.016 2.643 5.803 45.0
.041
.052
.071
.283
.804 2.355 5.257 SP 69 922.91 Rev. 9 50.0
.038
.047
.064
.248
.810 2.118 4.803 7/09/82 Page 21
n
~
m APPENDIX.
5 PE82 2 cf 5 SHORDIAM STATION - GAUSSIAN PIFF GAMMA (X*U/8) (1/N2)
ELEVATED RELEASE (H = 35 H) - DIVIDE RESULTS BY ONE MILI. ION MILES A
8 C
D E
F
~
G
.19 39.247 58.930 72.641 80.560 77.485 73.502 72.221
.25 25.949 46.090 61.884 79.208 80.137 75.124 72.785
.50 5.664 18.585 33.349 58.822 72.218 80.618 77.128
.75 1.290 9.651 20.805 43.178 58.763 75.802 80.544 1.0
.977 4.505 14.285 33.443 48.144 68.050 79.403 1.5
.699 1.601 8.119 22.308 33.933 53.808 71.608 2.0
.540
.789 5.280 15.910 25.994 43.099 63.938 7.5
.445
.609 3.734 12.098 20.979 36.032 57.228 3.0
.385
.512 2.797 8.639 17.331 31.518 51.451 3.5
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.445 2.182 7.931 14.744 27.932 46.651 4.0
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.395 1.757 6.688 12.788 25.018 42.635 4.5
.276
.357 1.443 5.743 11.254 22.482 39.179 5,0
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.327 1.212 5.014 10.032 20.422 36.256 7.5
.174
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.632 3.040 B.471 14.320 26.714 10.0
.136
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.400 2.085 4.670 11.060 21.300 15.0
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.217 1.178 2.812 7.472 15.242 20.0
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.787 2.121 5.564 11.951 25.0
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.584 1.671 4.430 9.880 30.0
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.471 1.389 3.699 8.474 l
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.387 1.184 3.167 7.427 l
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.820 2.206 5.454 SP 69.922.91 Rev. 9 7/09/82 Page 22
-- -. -. -..-. -.L -..-
m m
APPENDIX.. 5 Pegt 3 cf 5 SHOREHM STATION - GAUSSIAN P1FF GAffin (XeU/8) (1/M2) i i
ELEVATED RELEASE (H = 70 M) - DIVIDE RESUI.TS BY ONE MILI. ION MILES A
B C
D E
F G
.18 28.871 33.441 32.128 28.762 27.885 27.372 27.171
.25 21.688 31.315 33.466 30.080 28.482 27.582 27.265
.50 5.481 16.452 26.065 33.428 32.223 29.087 27.838
.75 1.282 8.211 18.126 30.384 33.434 31.300 78.744 1.0
.S73 4.391 13.055 28.114 31.873 32.973 29.989 l
1.5
.697 1.589 7.732 19.209 26.371 32.984 32.354 2.0
.539
.787 5.121 14.374 21.718 30.356 33.385 2.5
.445
.607 3.657 11.223 18.181 27.419 33.347 3.0
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.512 2.755 S.090 15.498 25.068 32.599 3.5
.339
.444 2.158 7.563 13.431 22.850 31.476 4.0
.304
.395 1.741 6.423 11.807 21.074 30.192 4.5
.276
.357 1.434 5.554 10.500 19.332 28.842 5.0
.253
.327 1.206 4.871 9.436 17.845 27.526 7.5
.174
.235
.820 2.990 6.229 13.083 22.183 10.0
.136
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.400 2.063 4.534 10.332 18.487 15.0
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.217 1.170 2.867 7.146 13.836 20.0
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.912 2.426 5.775 50.0
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.817 2.181 5.284 SP 69.$22.91 Rev. 9 7/09/82 Page 23
e m
^
APPENDIX 12 Page 4 of 5 SiOREHAM STATION - GAUSS 1pa! P1FF GAf814 (XeU/8) (1/M2)
ELEVATED RELEASE (H = 105 M) - D1 HIDE RESIA.TS 8Y OfE MILLION MILE 8 A
B C
D E
F G
.18 17.921 15.998 14.109 12.907 12.818 12.432 12.357 l
.25 18.204 17.623 15.548 13.309 12.818 12.508 12.383
.50 5.177 13.490 17.600 18.043 14.180 13.008 12.601
.75 1.267 7.521 14.463 17.823 18.022 13.734 12.901 1.0
.964 4.198 11.250 17.811 17.430 14.691 13.200 1.5
.693 1.565 7.122 15.042 17.661 16.737 14.235 2.0
.537
.781 4.857 12.160 16.216 17.827 15.262 2.5
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.604 3.524 S.909 14.493 17.823 16.249 3.0
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.510 2.681 8.240 12.896 17.387 17.048 3.5
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4.5
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.328 1.016 2.650 5.951 45.0
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.905 2.369 5.438 SP 69 922 91 Rev. 9 50.0
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.812 2.135 3.003 7/09/82 Page 24
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APPENDIX 12.."
Psgs 5 of 5 SIEREHAft STATION - GAUSSIAN P1FF GAf814 (NeU/8) (1/M2)
ELEVATED RELEASE (H = 140 M) - DIVbE RESULT 8 BY DIE Mll.1. ION MILES A
B C
D E
F G
.18 9.881 7.841 8.784 8.288 8.158 8.074 8.041
.25 10.931 8.996 7.408 8.480 8.247 8.108 8.057
.50 4.785 10.263 10.558 7.887 8.805 8.331 8.150
.75 1.245 8.662 10.812 8.371 7.655 8.834 8.283 1.0
.952 3.942 8.158 10.547 8.741 7.024 8.448 1.5
.888 1.530 6.357 10.770 10.499 8.108 6.835 2.0
.533
.773 4.512 9.651 10.531 9.381 7.274 2.5
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.600 3.345 8.341 10.621 10.273 7.786 3.0
.382
.506 2.578 7.195 10.007 10.714 8.358 3.5
..337
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.302
,.392 1.671 5.475 8.619 10.817 9.442 4.5
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.397 1.984 4.072 7.888 10.670 15.0
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NOM 0 GRAM No. 6
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SP 69.022.91 Rev. 9 7/09/82 Page 31 s
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SP 69 022 01 Rev. 9 7/09/82 Page 27
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l SP 69.022 01 Rev. 9 7/09/82 Page 33 l
MC-1 SubmittGdtI
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SP Number 69.021.01 Revision: 9 Date Eff.:7/09/82 TPC TPC TPC ONSITE SURVEYS a
1.0
- PURPO3E, l
l To describe the procedures used by the Onsite Radiological Monitoring Teams to conduct onsite radiological surveys and samplings during a radiological emergency.
2.0 RESPONSIBILITY l
The Radiation Protection Manager (RPM) is responsible for ensuring compliance with this procedure.
PPF 10.21.600-6.421
(
3.0 DISCUSSION 3.1 The main objective of an onsite survey is to collect dose rate and/or
(
environmental samples for site personnel protective action decision information.
3.2 Emergency organization staffing is such that one team will be available at ALERT or higher emergency levels.
3.3 Summary of Overall Sequence of Actions:
3.3.1 RPM or designee, call the OSC Supervisor for manpower and team assignment 3.3.2 Survey team report to the TSC for briefing 3.3.3 Af ter briefing, team members pick up equipment at the OSC or EP Access Control Point, and perform predeployment checks of equipment 3.3.4 At the preselected locations onsite, the survey team performs survey and sampling as required 3.3.5 Returning to the station, the survey team turns in ssmples to the Rad / Chem Lab and reports data back to the RPM at the TSC.
3.3.6 Topics covered in this procedure:
Page 8.1 RPM / Designee Actions 3
8.2 Onsite Survey Team - Equipment Check 4
8.3 Onsite Survey Team - Survey 75 Appendix 12.1 Onsite Survey Briefing Form, SPF 69 021 01-1 Appendix 12.2 Onsite Survey Equipment Assembly Cuide, SPF 69 021 01-2 Appendix 12.3 Onsite Survey Eata Sheet, SPF 69 020 01-3 Appendix 12.4 Onsite Survey Map 4.0 PRECAUTIONS N/A 5.0 PREREQUISITES 5.1 An ALERT or higher emergency classification has been reached, and the Emergency Director or the RPM has determined an onsite survey is neesssary.
6.0 LIMITATION AND ACTIONS 6.1 Onsite survey activities are limited to areas within the Protected Area Fence but outside of plant buildings.
t SP 69 021.01 Rev. O 7/09/82 Page 2
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7.0 MATERIAL AND EQUIPMENT Se'e Appendix 12.2, Onsite Survey Equipment Assembly Guid'e.
(
8.0 PROCEDURE 8.1 RPM / Designee Actions 8.1.1 Call the OSC Superviso'r to form an Onsite Survey Team, and have the team report to TSC for briefing.
8.1.2 Complete the Onsite Survey Briefing Form (Appendix 12.1) to the fullest extent possible (see 8.1.4, 8.1.5, and 8.1.6).
8.1.3 Brief the team accor' ding to the Onsite Survey Briefing Form-- -' ~
~
(Appendix 12.1).
Based on survey results desired, instruct the team on what equipment to carry out, using the Onsite Survey Equipment Assembly Guide *(Appendix 12.2) and have them check out the required items.
8.1.4 Protective Equipment 8.1.4.1 Require team to carry full-face mask protection for all emergencies where an airborne release is known to have happened or is impending.
8.1.4.2 When airborne release reaches the GENERAL EMERGENCY level or when the projected I-131 concentration at the protected area fence is 3 x 10-6 uCi/cc or greater,
(
implement SP69.951.WI, Thyroid Blocking to see if there is a need for KI administration.
8.1.4.3 Required donning of Hoods, Booties, Coveralls, and Gloves when airborne release occurs with prevailing precipitation. Use judgment in other cases (consider stability class and emergency 1cvel, etc.).
8.1.5 Exposure / Dose Limits 8.1.5.1 Normal health physics exposure limits described in SP61 012.91, Personnel. Dose Limits and Guides apply for all members of the onsite surtsy team.
8.1.5.2 If for any reason the above limits must be raised, refer to SP69.959.91, Radiation Dose During an Emergency for authorization and limits.
8.1.6 Communications _
8.1.6.1 Make sure the team has obtained a radio from the OSC Supervisor and has designated a channel to be used.
SP 69.921.91 Rev. 9
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7/09/82 Page 3 m.__-__-____
8.1.6.2 Designate o tecm ID prict to cur,vsy tcam departure.
8.1.6.3 Maintain proper communications contact (identification,
(
location at all times).
NOTE:
If communications problems arise, suryey team members can utilize plant extension phones or PA system because of close proximity to the plant.
8.1.7 If conditions warrant, outline for the survey team a route to approach the desired survey points with minimal erposure or safety risk. Mark this route on the Onsite Survey Map (Attachment 12.4).
8.2 Onsite Survey Team - Equipme't Check n
8.2.1 Af ter briefing, proceed to assemble the necessary survey and protective equipment as dhecked off on Appendices 12.1 and 12.2.
Pick up survey instruments at the OSC, HP Access Control Point, or elsewhere as directed by the Dispatcher.
8.2.2 Perform battery checks and operational checks on all equipment gathered; also check calibration dates.
8.2.3 Log predeployment personnel dosimeter readings onto the Onsite Survey Briefing Form ( Appendix 12.1, item 11).
8.2.4 lf air sampling is required, perform the following steps, otherwise proceed to Step 8.3.
(
~
8.2.4.1 Install a particulate filter and a Silver Zeolite cartridge on the RADeCO air sampler:
A.
Use an open-face combination filter / cartridge holder; B.
Mark flow direction on the filter paper before installation.
8.2.4.2 Af ter installation, check that filter is centered, has no tears or damage, and that both the filter and the cartridge are properly oriented and sufficiently tightened to prevent by pass leakage.
8.2.4.3 Turn on the air sampler and observe the flow rate in the proper range.
For the RADeCO unit, this is about 2-3 CFM.
8.2.4.4 Turn off the unit after checking and leave the filter / cartridge holder on the unit. Wrap the holder with a plastic bag to prevent contamination prior to sampling.
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SP 69 021 01 Rev. 0 7/09/82 Page 4
8.3 Onsito Survay Tera - Survey 8.3.1 Proceed to the posted survey point following routes depicted on the Onsite Survey Map ( Appendix 12.4).
8.3.2 While enroute: keep a survey instrument on and begin recording periodic open-window readings of 2 mR/hr or greater on,the' Onsite Survey Data Sheet (Appendix 12.3). Assign a number to any non-fixed points sequentially (starting with f17 and on).
Mark the location and the number on the map, then enter the number and the exposure rate onto Actscheent 12.3.
Take note of any abnormal avents or conditions and record on Appendix 12.3.
8.3.3 Upon arrival at the survey point:
8.3.3.1 Downscale the survey meter to read the W.B. dose rate or the exposure rate first. Check readings at 3" and 4' off the ground with window open and closed.
Record results on Appendix 12.3.
8.3.3.2 If air samples are not required, proceed to the next point and repeat steps 8.3.1 through 8.3.3 for all required survey points, then go to Step 8.3.5.
8.3.4 Air Sampling 8.3.4.1 Set sampler timer to 10 minutes, and place the sampler at
(
about 4 feet above the ground. The RADeC0 unit may be operated in any position provided that the intake and exhaust ports are free of obstructions. Taka plastic wrap off the sample holder.
8.3.4.2 Start the sampler. Record start time and flow rate on Appendix 12.3.
Monitor the run time to 10 minutes.
8.3.4.3 During the sampler run time, continue monitoring the dose rates in,the vicinity and record any significant variations.
8.3.4.4 Before the sampler stops, note the final flow rate.
Enter this and the stop time onto Appendix 12.3.
Assign a ID number to the sample.
If there is no more air sampling to do, place the entire sample holder into a plastic bag and mark the ID number on it.
Otherwise retrieve the filter / cartridge and replace with new ones.
Put the filter and the eartridge into separate bags and label them properly with the ID number.
8.3.5 When all completed, return to the EP Access Control Point. Remove protective clothing.
Frisk each other out and check equipment / cart SP 69 921.91 Rev. @
7/09/82 Page 5
for possiblo contccinatien.
Bag cny item surpacted cf being contaminated.
If contamination is found, call the RPM at the TSC for further instructions.
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8.3.6 Return samples to the Rad / Chem Lab for analysis. Note post-survey dosimeter readings on Appendix 12.1 and report with all survey data sheets to the RPM at,the TSC.
8.3.7 Report back to the OSC Supervisor.
9.0 ACCEPTANCE CRITERIA N/A 10.0 FINAL CONDITIONS 10.1 The RPM / designee shall, after ciamining them, forward all survey records to the Administrative Section for filing in accordance with permanent plant procedures.
10.2 Rad / Chem Lab and Health Physics: All samples and contmainated objects should be handled according to pertinent regular plant procedures.
10.3 All survey equipment should be returned to the original storage place in ready-to-use condition unless contaminated and being handled as outlined in 10.2 above.
11.0 REFERENCES
(
11.1 LILCO Shoreham Nuclear Power Station Emergency Plan i
11.2 SP 61 012 01, Parsonnel Dose Limits and Guides 11.3 SP 69 959.91, Radiation Doses During an Emergency 11.4 SP 69 939 91, contamination control During Emergencies 11.5 SP 69 951 01, Thyroid Blocking 11.6 RADeC0 Portable Battery Powered Air Sampler Instruction Manual, Sci. Appl.,
Inc. September, 1980 12.0 APPENDICES 12.1 Onsite Survey Briefing Form,.SPF 69 921 91-1 12.2 Onsite Survey Equipment Assenbly Guide, SPF 69 921.91-2 12.3 Onsite Survey Data Sheet, SPF 69 921.01-3 12.4 Onsite Survey Map k
SP 69 921 91 Rev. 9 7/09/82 Page 6 G
_____________._____.__.____________________.__.____._______.___._.]
Appc5 dix 12.'
ONSITE SURVEY BRIEFING FORM
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1.
Date:
Time:#
Briefing at:
Team ID:
2.
Survey requested by:
Briefed by:
3.
Nature of Release:
Ground:
Elevated;_
Unkn.
4.
Unusual Area /Env. Conditions:
5.
Communication Extensions:
RPM-TSC:
OSC:
C. Rm:
6.
a.
Primary Downwind Sector:
Adjacent Sectors:
b.
Survey Locations / Points:
7.
Projected WB dose rates at survey area (if available):
At Pt Sector Dose Rate ar/hr At Pt Sector Dose Rate ar/hr At Pt Sector Dose Rate ar/hr 8.
Team member names & authorized doses (rem):
Lead dose
(
Asst.
dose rem
^^
rem 9.
Protective Equipment (check applicable):
(1)
Dosimeters (200 mR & SR)
(5)
Glove Other (2)
TLD (WB)
(6)
Bootie (3)
F.F. Mask w I/P Canister (7)
KI (4)
Coverell (8)
Hood 10.
Survey data ! be Lollected:
(1)
- 'W e Body Dose Rates (2)
I' __~ c I/P Sample (3)
Gross Beta / Gamma cpm or Exposure Rates (4)
Other (Specify) 11.
Team dosimeter readings (Before/After Mission):
Lead (200 mR Scale)
/
,: (SR Scale)
/
Asst. (200 mR Scale)
/
' ; (SR Scale)
/
12.
Special Instructions:
SPF 69 021 01-1 Rev. O l
SP 69 021 01 Rev. 0 7/09/82 Page 7
I Appsudix 12.2 ONSITE SURVEY EQUIPMENT ASSEMBLY GUIDE
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1.
RO-2A 2.
Victoreen 496 w/EP-270 Probe 3.
Eberline RM-14 w/EP-210 Probe 4
A.
RADeC0 battery powered air sampler B.
Open-face combihation filter and cartridge holder for --- -
above air sampler C.
Particulate filter papers and Silver Zeolite cartridges for above air p9,.er D.
Plastic bags with labels for sealing up the air samples collected E.
Onsite Survey Cart for mounting the air sampler and its battery 5.
Radio with carrying belt 6.
Flashlight (s) (for night or dawn only)
- 7. -
Clipboard.with:
, e This procedure with Attachment I completed as far as possible a.
b.
Marking pancil 8.
Other (specify below):
SPF 69 921 01-2 Rev. 9 l
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SP 69 921.91 Rev. 9 7/09/82 Page 8
l Appandix 12.3 ONSITE SURVEY DATA SHEET 1.
Team members:
Date:
^'
2.
Time survey started:
Time survey completed:
3.
Survey meter /probel type:
4.
Survey Results:
Time Location / Survey Pt.
Et. Above Gnd. Window-Open Window-Closed 5.
Air Samples:
Time Location / Survey Pt.
Sample ID# Time Start /End Flowrate Start /End
/
/
/
/
/
/
6.
Notes / Remarks:
SPF 69 921 01-3 Rev. $
SP 69.021.01 Rev. 9 7/09/82 Page 9
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SP Number: 69.020.01 Revision:
0 Date Eff.
7/09/82 TPC TPC TPC DOWNWIND SURVEYS 1.0 PURPOSE To describe the procedures used by the Offsite Radiological ';nitoring (ORM) teams to conduct downwind radiological surveys and sa:plings during an emergency.
2.0 RESPONSIBILITY The Radiation Protection Manager (RPM)/ Radiological Control Manager (RCM), shall be responsible for ensuring compliance with this procedure.
PPF 1021.600-6.421
1 3.0 DISCUSSION 3.1 Depending upon the elass of emergency declared, the Radiation Protection
(
Manager in the Technic'al Support Center (TSC) or the Radiological Control Manager in the Emergency Operations Facility (EOF), shall direct the activities of the Offsite Radiological Monitoring (ORM) teams. At the ALERT level class, the TSC is activated and RPM will direct any ORM teams dispatched. The RPM will continue to have command of the ORM teams until notified by the RCM that the EOF is activated, (usually Site Area and General classes of Emergency) at that time, the RCM is ready to assume control of offsite monitoring activites.
3.2 There are five major reasons for sending cat an ORM team; it may be any one, or any combination, of the following:
3.2.1 To provide or confirm radiological EAL data at the appropriate site bounda ry.
3.2.2 To track down or verify the location, size and direction of a radioactive plume if there has been an airborne release.
3.2.3 To provide or confirm dose or exposure rates inside the plume exposure zone, which are needed by the Dose Assessment Group for protective action recommendations.
NOTE:
Dose or exposure rates include whole-body and inhalation (thyroid), at the plume centerline and the plume boundaries.
(
3.2.4 To provide samples (air, soil, vegetation, etc.) taken fro = within the plume exposure zone, which will enable the Rad / Chem Lab staff to determine the plume composition and hence aid them in the further analysis of the release characteristics.
3.2.5 To check surface conta=ination, if any, that is above acceptable limits, due to fallout or precipitation from the plume within the plume exposure zone, for exposure control and recovery planning.
3.2 Staf fing and emergency organization are such that one ORM team shall be available at ALERT level and two more available at SITE AREA or GENERAL EMERGENCY level.
3.3 then and where to send an ORM team is important.
Selection of survey and sanpling locations should consider the prevailing wind speed, and the estiaated time of plume arrival over the selected area vs ORM team travel time.
NOTE:
Routes planned for the team should avoid those utilized for planned or effected evacuation.
3.4 If extended duty for survey teams is anticipated, the Dispatcher should consider and coordinate efforts to relieve field teams at reasonable i
SP 69.020.01 Rev. 0 7/09/82 Page 2 f
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intervals.
Ha may also decide to dispat'ch parsonnel to meet a team in the field to:
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3.4.1 Retrieve air or other environmental samples for detailed and timely lab isotopic analysis, and/or:
3.4.2 Replenish the teams with needed fresh supplies while keeping them in a mobile, field position.
3.5 For SITE AREA and GENERAL EM2RGENCIES, at leaste one ORM team must be deployed within 60 minutes of the emergency declaration.
3.6 Summary of Overall Sequence of Actions 3.6.1 Dispatch from TSC:
3.6.1.1 RPM /desf ynee issues an ORM request to the Dispatcher.
3.6.1.3 After having received a radio from OSC Supervisor, the team reports to the TSC for briefing with the dispatcher.
3.6.1.4 Af ter briefing, team members pick up equipment at the Main Security Bldg. and perform pre-deployment check of equipment and vehicle.
3.6.1.5 Before departure, ORM team establish radio communication l
[
with the Dispatcher and proceed according to preplanned routes to the survey area.
3.6.1.6 At preselected locations offsite, the ORM team performs survey and sampling as required.
3.6.1.7 Upon termination of mission, the ORM team returns to the site to submit survey records to the Dispatcher and turn in samples to the Rad / Chem Lab., check for equipment contamination and take note of individual exposure records.
3.6.2 Dispatch from EOF:
3.6.2.1 RCM/ designee issues an ORM request to the dispatcher.
3.6.2.2 The Dispatcher at EOF calls available manpower for team assignment.
3.6.2.3 The team reports to the EOF for briefing with the Dispatcher.
[
SP 69 020 01 Rev. 0 7/09/82 Page 3
3.6.2.4 Af ter briefing, team cembers pick up equipstnt at the EOF and perform pre-deployment check of equipment and vehicles.
(
3.6.2.5 Sefore departure, team establishes radio communication with the Dispatcher and then proceeds according to preplanned routes to the survey areas.
3.6.2.6 At preselected locations of fsite, the ORM team performs survey and sampling as required.
3.6.2.7 Upon ter=ination of mission, the ORM team returns to the site, or EOF, to submit survey records to the Dispatcher and turn in samples to the Rad / Chem Lab, check for
. equipment contaminaticn and take note of individual exposure records.
3.7 Topics covered in this procedure:
Page 8.1 RPM / Designee Actions 5
8.2 RCM/ Designee Actions 5
- 8. 3 ORM Dispatcher Actions 5
8.4 ORM Team Members-Equipment Check 6
8.5 ORM Team - Survey 7
8.6 ORM Team - Air Sampling 8
- 8. 7 ORM Team - Continuation 9
8.8 ORM Team - Conclusion of Survey 9
Appendix 12.1 ORM Briefing Form Appendix 12.2 ORM Ki Inve nto ry Appendix 12.3 ORM Data Sheet 4.0 PRECAUTIONS N/A 5.0 PREREOUISITES 5.1 An ALERT or higher Emergency Classification has been reached and an ORM request has been issued by the RPM /RCM.
5.2 The Dispatcher has gathered the necessary information to brief the ORM team (ORM Briefing Form, Appendix 12.1 and Offsite Survey Map).
6.0 LIMITATION AND ACTIONS 6.1 Site-respansible ORM activities are generally limited to within the 10 mile Emergency Planning Zone.
7.0 MATERIAL AND E0"1PMENT 7.1 Off site Radiological Monitoring (ORM) Kit k
SP 69.020.01 Rev. 0 7/09/82 Page 4
8.0 PROCEDURE 8.1 RPM / Designee Actions
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8.1.1 Check that Prerequisites 5.1 and 5.2 are met.
If -- Dispatcher is on duty, assign one.
Dose Assessment Staff #1 n.
.lly will be designated as the Dispatcher.
8.1.2 Contact OSC Supervisor for for=ation of an ORM team, and have team members assemble at the TSC for briefing. Team should obtain a radio from the OSC Supervisor prior to the briefing.
8.2 RCM/ Designee Actions 8.2.1 If ORM activities are initiated at the EOF, perform Step 8.1.1 above and form an ORM team at the EOF.
- 8. 3 ORM Dispatcher Actions 8.3.1 Complete Appendix 12.1 to the fullest extent possible.
(See 8.3.4, 8.3.5 and 8.3.6).
8.3.2 On the Of fsite Survey Map, outline a route to be followed by the team. An Offsite Survey Fbp for the tea = is located both in the company vehicle and ORM Kit.
8.3.3 Brief the team according to Appendix 12.1.
Describe the release situation and types of survey / sampling desired over the survey area.
8.3.4 Protective Ecuipment
.1 Instruct team members to put on Full-face Mask when projected 1-131 concentrations at downwind survey locations exceed 3 x 10-7.pCi/cc.
NOTE:
For ORM activities near the site boundary, use Full-face Mask protection for all emergencies where an airborne release is know to have happened or is impending.
.2 For additional protection against thyroid exposure to radioiodines, execute SP 69.051.01, Thyroid Blocking, when either one of t he following conditions is met, to determine whether there is a need for K1 administration:
When a General Emergency is declared based upon exceeding a.
radiological EAL's.
b.
When projected downwind survey area I-131 concentration is 3 x 10-6,pci/cc or greater.
g SP 69.020.01 Rev. 0 7/09/82 Page 5
.3 Consider donning of Hoods, Booties, Covarcils, and Giovas when cirborna release occurs with precipitations.
Use judgement in other cases.
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8.3.5 Personnel Dose Limits If for any reason nor=al health physics exposure limits described in SP 61 012 01, Personnel Dose Limits and Guides must be raised for survey team members, refer to SP 69 050.01, Radiation Doses During An Ecergency, for authorization and limits.
8.3.6 Communications
.1 Make sure the team has obtained a radio from the OSC Supervisor and has a designated channel to be used.
.2 Remind team to radio in prior to departure to report team color code ID (from the ORM Kit).
.3 ORM Dispatcher, use the following in radio communication to identify self:
At TSC: "Shoreham Dispatcher TSC" At EOF: "Shoreham Dispatcher EOF" 8.3.7 After the briefing, designate a company vehicle for the team and provide the key or keys.
8.4 ORM Team Members - Ecuirment Check
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8.4.1 ORM Tech. (Team Leader)
ORM Tech. has the responsibility of operating the Survey and Sa=pling equipment to obtain required results.
8.4.2 ORM Asst. (Team Me=ber)
ORM Asst. has the responsibility of driving, logging results, and radio coc=unication.
Give assistance to the ORM Tech. when situation requires.
8.4.3 Ensure that survey points and routes to be taken as well as all needed infor=ation on Appendix 12.1 is filled out.
Locations of survey points are both in the cc pany vehicle and ORM Kit.
8.4.4 Proceed to the Main Security Building / EOF to sign out an ORM Kit.
8.4.5 Replenish any missing items f rom the inventory list.
Install batteries if necessary.
Perform source checks to observe proper ceter response.
Check equip ent calibration stickers.
SP 69 020.01 Rev. 9
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7/09/82 Page 6 l
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1
8.4.6 Use an AC source to check the TCS EAS-1 Air Sampler motor.
Do not put on the filter canister.
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8.4.7 Log pre-survey pocket dosimeter readings on Appendix 12.1.
8.4.8 Don protective clothing and dosimeters as required.
8.4.9 Proceed to the survey vehicle.
Check for gas, cigarette lighter socket, lights, and operability.
Start the engine and with it on, plug in the cable of the TCS EAS-1 Air Sampler (w/o the filter) and observe proper running (it should sound like a small vacuum cleaner).
If airborne release has occurred, check outside of vehicle for possible contamination (see 3.8.3).
8.4.10 ORM Asst., establish radio com=unication with the Dispatcher, report the Teams's ID (color code on the ORM Kit picked up) and that the team is ready.
- 8. 5 ORM Team - Survey 8.5.1 Proceed to the survey point using Offsite Survey Map.
8.5.2 While enroute: keep the RM-14 with HP-270 probe on and begin recording periodic readings of 1 mR/hr or greater on Appendix 12.3.
(Assign a nember to such non-fixed points sequentially, mark the location and exposure rate reading on the map, then enter the point number assigned and the exposure rate on Appendix 12.3.
NOTE:
Report any abnormal events or conditions co the
(,
_.. _... Dispatcher via radio.
- 8. 5. 3 Upon arrival at selected survey points, report to the Dispatcher with time and survey point number.
8.5.4 If plume tracking is not required, proceed to Step 8.5.7.
8.5.5 If " Plume Center Exp/ Dose Rates & Location" (item 10 on Appendix 12.1) is checked, continue driving until the dose rate (open-window) appears to peak and begins to decrease.
Return to the peak concentration area.
S.S.C Report the maximum plume W.B. dose rate measured at 3 feet above the ground and the measurement location to the Dispatcher i= mediately, cnd mark this location on the map as well.
8.5.7 At the first survey location, obtain gamma measurements (closed-window) at 3 inches and 3 feet above the ground, and record these readings on Appendix 12.3.
.1 If the 3 feet reading is noticeably higher than the 3 inch reading, it should be assumed that the predominant gamma source is the airborne plume.
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SP 69.020.01 Rev. 0 7/09/82 Page 7
7 f
.2 If readings increase with decreasing height above the ground, assume that source is on the surface.
In this case, take several smear samples (with gloves) of the' ground, and/or a
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soil sample when conditions permit.
.3 Use a plastic bag for the soil sample and fill out a label to tag the bag.
Label the envelopes for the smears with proper ID information.
.4 Periodically check beta reading at 3 inches and 3 feet above ground with probe window open.
Record any readings significantly different from the window-closed readings.
8.6 ORM Team - Air Sampling 8.6.1 Obtain an air sample in center of the plume or at the fixed survey point as required (Appendix 12.1, item 10).
8.6.2 Leaving the vehicle engine running, plug in the TCS EAS-1 Air Sampler and run it for about 1/2 minute warm-up period without the filter / canister.
8.6.3 Pry open the quart can containing the canister.
If the moisture check det inside the can is not blue, replace lid and open another.
Turn off the warmed up sampler and center the canitter over the suction opening on the side of the sampler.
Stretch the elastic retainer over the outer end of the canister and make sure the fit is tight.
8.6.4 Sampler should be placed or held about 4 feet above the ground away from the vehicle exhaust pipe.
NOTE:
The ORM vans are equipped with a slide mount for the TCS Air Sampler to allow sampling from inside the van.
8.6.5 Set the timer for 5 minutes and adjust the flow rate to 5 CFM.
Use a stop watch to verify run time is 5 minutes + 6 seconds.
8.6.6 When the air sample is completed, carefully remove the canister from the sampler and put it in a plastic bag.
Avoid contacting the white filter cloth outside around the bare filter.
Record start /stop times and flow rates on Appendix 12.3.
8.6.7 Connect the brass-shell CM-1 probe with a cable to the RM-14 count rate meter " DETECT 0E" input ENC.
Switch " RESPONSE" to " SLOW".
In this position, allow 20 seconds meter response time at each measurement.
8.6.8 Using the above setup, measure the background at 4 feet above the ground or inside the vehicle.
Record this background cpm on Appendi:c 12.3.
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SP 69.020 01 Rev. 0 l
7/09/82 Page 8 l
1
8.6.9 Insert the CM-1 probe into the center hole of the canister and downscale the RM-14 as necessary.
Record the stabilized filter / canister reading (cpc) on Appendix 12.3.
Remove the CM-1 probe.
8.6.10 Carefully remove the white fiber cloth which is wrapped around the canister by pulling down the red tape.
Hold the canister in the plastic bag while doing this to avoid contacting the cloth, and to prevent silver gel crystal bits from falling out af ter the cloth wrapping is removed.
Return the fiber cloth to the quart can.
8.6.11 Insert the CM-1 probe into the center hole of the canister and record the stabilized bare cannister reading and time of measurement on Apendix 12.3.
8.6.12 Place the bare canister with the plastic bag into the quart can.
I Put a label marked with the proper time, date, and sample #
information on the sealed can.
Air sample #'s should be assigned sequentially.
8.6.13 Report the information on Appendix 12.3 to the Dispatcher by radio.
8.6.14 If plume tracking is not required, go to Step 8.7.1 below.
Otherwise, continue to drive through the plume and identify the l
other boundary of the plume (exposure rate, window open, at approximately 1 mR/hr).
At this boundary, record and report the exposure or dose rate measured, and the location, to the Dispatcher.
8.7 ORM Team - Continuation
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8.7.1 Check personnel pocket dosimeter readings and number of canisters re=aining before continuing on.
Report any over-exposure or shortage.
8.7.2 Continue on to the next survey point as preplanned and repeat Steps 8.5 through 8.7 or as otherwise directed by the Dispatcher.
8.8 ORM Team - Conclusion of Survey 8.8.1 When all survey and sampling activities are completed and the team receives no further ORM request through the Dispatcher, or the team is relieved by a second team, conclude the mission and return to the station unless instructed otherwise by the Dispatcher.
NOTE:
If team is to return to EOF, reques; suitable locations to perform Steps 8.8.2 through 8.8.7, and report back to the RCM instead of the OSC Supervisor.
8.8.2 Upon arrival, notify the Dispatcher and take the site access road near the LILCO 69KV substation.
Stop before the substation and perform a contamination check of the vehicic (inside and cutside) using the RM-14/HP-210
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SP 69.020.01 Rev. 0 7/09/82 Page 9
8.8.3 If. gross beta and ga=ma counts exceed 50 cpm above background, call in and wait for decontamination or other instructions / assistance from the Dispatcher (Reference SP 69 030 01, Contamination Control
(
During Emergencies).
8.8.4 If vehicle checks out clean, remove protective clothing and return to the Main Security Building.
8.8.5 Bag clothing, used masks and equipment suspected of being contaminated.
Replenish ORM Kit items and return it in ready-to use ccndition.
8.8.6 Frisk out each other using the RM-14/HP-210 Frisk samples brought back to check for unusually high deposits before transporting to Rad / Chem Lab area for analysis.
- 8. 8. 7 Send all sa=ples and bagged items in 8.8.5 to the Rad / Chem Lab.
8.8.8 Record post-survey dosimeter readings on Appendix 12.1, and send all records and data sheets to the Dispatcher.
8.8.9 Report back to the OSC Supervisor.
Mission completed.
9.0 ACCEPTANCE CRITERIA N/A 10.0 FINAL CONDITIONS
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10.1 The Dispatcher shall examine all records and data sheets turned in by the team, make copies of those needed for dose assessment activities and forward all records to the Administrative Section for filing in accordance with permanent plant procedures.
10.2 Rad / Chem Lab and Health Physics:
All field samples and contaminated clothing and equipment should be disposed of or decontaminated according to regular plant procedures.
11.0 REFERENCE 11.1 LILCO Shoreham Nuclear Power Station Emergency Plan 11.2 SP 69.050.01, Radiation Doses During An Emergency 11.3 SP 69 030 03, Contamination Control During Emergencies 11.4 SP 69.051.01, Thyroid Blocking l
11.5 SP 61 012 01, Personnel Dose Limits and Guides 1
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SF 69 020 01 Rev. 0 7/09/82 Page 10
2 12.0 APPENDICES 12.1 Offsite Radiological Monitoring (ORM) Briefing Form, SPF69.020.01-1 f
12.2 Offsite Radiological Monitoring (ORM) Kit Inven tory 12.3 0ffsite Radiological Monitoring (ORM) Data Sheet, SPF 69 020 01-2 j
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SP 69 020 01 Rev. 0 7/09/82 Page 11
Appendix 12.1 0FF-SITE RADIOLOGICAL MONITORING (ORM) BRIEFING FORM
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l.
Date:
Time:
Briefing at:
2.
Survey requested by:
Briefed by:
3.
ORM Dispatcher:
Back-up Tel #:
- 4.
Team Radio Ch:
Tea = 1D: "Shoreham 5.
Alternate Communication Tel. #:
RPM-TSC:
RCM-EOF:
CONTROL RM:
6.
- a. Primary Downwind Sector:
Adjacent Sectors:
- b. ORM/ Survey Locations / Points:
7.
Projected WB dose rates at survey area (if available):
At ORM Pt Sector Dist mi, D/R mr/hr At ORM Pt Sector Dist mi, D/R or/hr At ORM Pt Sector Dist mi, D/R mr/hr 8.
Team cember names and authorized doses (rec):
ORM Tech:
, dose rem
(
ORM Tech:
, dose rem 9.
Protective Equipnent (check applicable):
(1)
Dosi=eters (200 =R & SR)
(5)
Glove Other (2)
TLD (WB)
(6)
Bootie (3)
F.F. Maks w 1/P Canister (7)
KI (4)
Coverall (8)
Hood 10.
OFM data to be collected:
(1)
Plume Center Exp./ Dose Rates & Location (2)
Pluce Center Air I/P Scmple (3)
Plume Boundaries down to 1 =R/hr (4)
Other (Specify) 11.
Team dosh2tcr readings (Before/Af ter Mission):
ORM Tech. (200 mR Scale)
/
- (5R Scale)
/
ORM Asst. (27,3 tR Scale)
/
- (5R Scale)
/
12.
Special Instructions:
SPF 69 020 01-1 Rev. 0 k
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SP 69.020 91 Rev. O j
7/09/82 Page 12
Appendix 12.2 OFF-SITE RADIOLOGICAL MONITORING (ORM) KIT INVENTORY
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1.
(1)
Eberline R0-2A 2.
(1)
Eberline RM-14 w/HP-270 Probe 3.
(1)
Eberline RM-14 w/HP-210 Probe 4.
(1)
TCS EAS-1 Air Sampler w/one GM-1 Probe and 3 Canisters 5.
(6)
Spare TCS Air Sa=pling Canisters 6.
(1)
Shield Assy w/SH-4 Sa ple Holder 7.
(100) Smears and Envelopes 8.
(50) Plastic Sample Bags with Labels 9.
(1)
Check Source 10.
(2)
Flashlight w/ Spare Bulb 11.
(1)
Portable 2-Way Radio (in Survey Van) 12.
(1)
Roll of Dimes, 50 per Roll 13.
(1)
Roll of FMsking Tape 14.
(1)
Clipboard with:
a.
This Procedure b.
Completed ORM Briefing Form c.
Survey Locations Diagram (Map) d.
(5) ORM Data Sheets (Blank)
(2) Writing / Marking Pens e.
15.
Protective Equipment:
a.
(2) 0-200 =R, (2) 0-5R Pocket Dos ime te rs b.
(2) Personnel TLD, (1) Control TLD (1) DRD Dosimeter Charger c.
d.
(2) F.F. Ultraview Mask w 1/P Filter Canister i
e.
(1) Vial of KI f.
Pro ~tective Clothing, 2 each, of; Coveralls Pairs of Gloves w/ Liners Pairs of Booties Hoods 16.
Environ = ental Station:
(1) Key (2) Replacement TLD 17.
Spare Batteries, 4 each, of; AA Size A Size B Size C Size D Size
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SP 69.020.01 Rev. 0 7/09/82 Page 13
Appendix 12.3 0FF-SITE RADIOLOGICAL MONITORING (ORM) DATA SHEET
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1.
Team Members:
Date:
2.
Time Dispatched Time Returned l
3.
Air Sample Data 4.
Dose Rate Measurements l
AIR SAMPLE #:
iOW lC W HT.
1 Location (Mark Map)
Survey Exp. Rate Exp. Rate above Canister #
Point (mR/ht)
(mR/hr) grnd Time.
Start /Stop
/
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Flow Rate: Start /Stop
/
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j Background (cpm)
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i Filter / Canister Reading (cpm) i l
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I Bare Canister Reading (cpm)
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i Time of Measurement (24 hr clock) i I
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- REPORT ALL VALUES TO THE DISPATCHER i
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1 AIR SAMPLE #:
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1 Location (Mark Map) 4 Canister #
Tice :
Start /Stop
/
i Flow Rate: Start /Stop
/
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i Background (cpm)
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Filter / Canister Reading (eps)
Bare Canister Reading (cpm)
Ti=e of Measurement (24 hr clock) i i
- REPORT ALL VALUES TO THE DISPATCHER i
I AIR SAMPLE #:
i i
Location (Mark Map) i Canister #
Time:
Start /Stop
/
Flow Rate: Start /Stop
/
i Background (cpm)
Filter / Canister Reading (cpm)
Bare Canister Reading (cpm)
I Time of Measurement (24 hr clock) i
- REPORT ALL VALUES TO THE DISPATCHER i
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I SPF 69.020.01-2 Rev. 0 i
k SP 69.020.01 Rev. O 7/09/82 Page 14
. - 14 Submitted:
1 ff., I - 1 Reviewed /0QA ngr jh wp Approved / Plant Mgr.:
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SP Number 69.026.01 Revision: 0 Date Eff.: 7/09/82 TPC TPC TPC PROTECTIVE ACTION RECOMMENDATIONS
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1.0 PURPOSE This procedure provides guidelines for determining protective action recommendations to be given to offsite authorities.
2.0 PISPONSIBILITY The Radiological Control Manager, Radiation Protection Manager or In plant Radiation Monitoring Technician is responsible for ensuring compliance with this proced' ire.
PPF 1021.63Z-6.'+21
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3.0 DISCUSSION I
3.1 The decision process used in determining a recoc= ended protective action is based upon a number of factors. These factors are: release duration; cagnitude of release; plume travel ti=e; evacuation time estimates; dilution factors; shelter factors; dose limits; and dose savings.
3.2 Af ter determining a protective action, the Response Manager / Emergency Director will give approval to such an action before it is recommended. to offsite authorities.
3.3 Radiological Control Manager / Radiation Protection Manager or his staf f cay be available to perform this procedure for dif ferent distances used in SP69 022.01 Deter =ination of offsite Doses.
This procedure explains the methodology for deter =ining protective actions for points sequentially.
3.4 Topics covered in this procedure include:
Page 8.1 Waterborne Protective Actions 3
8.2 Airborne Protective Actions 4
Appendix 12.1 - Waterborne Protective Action Guidance Chart Appendix 12.2 - Airborne Protective Action Guide Worksheet, SPF69.026.01-1 Appendix 12.3 - Evacuation Ti=es by Wind Direction Appendix 12.4 - Shielding Factors f rom a Ca=ca Cloud Source k
Appendix 12.5-- Thyroid-and Whole Body Guidance Charts Appendix 12.6 - Prctective Action Map, SPF69.026.01-2 4.0 PRECAUTIONS Because protective action reco=mendations could be influenced by factors not considered here, use this procedure with co= mon sense and judgement.
5.0 PREREOUISITES SP69.?22.01, Deter =inatier. of Offsite Doses and/or SP69 024 01, Waterborne Release Dose Pro jection have been initiated.
6.0 LIMITATIONS AND ACTIONS The Energency Director / Response Manager ust approve of a protective action before it is given to offsite authorities.
7.0 MATERIALS AND EQUIPMENT N/A
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SP 69 026.01 Rev. 0 7/09/82 Page 2
8.0 PROCEDURE
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\\
8.1 Waterborne Protective Actioris,
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8.1.1 Dose Assessment Staff Member or In plant Radiation Monitoring Technician, performth(following:
\\
8.1.1.1 Compare projecipd swimming (whole body and skin) and boating doses ottained from SP 69.024.01, Waterborne Release Dose Pro'ection with the Waterborne Protective Action Guidance Chart (Appendix 12.1).
After consultation kith the Radiation Protection Manager 8.1.1. 2
/ Radiological Controix Manager (if available), give the filled out worksheets'(Appendix 12.1 and SPF 69.024.01-1) to the Emergency Director / Response Manager for subsequent approval and transmission to offsite authorities in accordance with SP69.009.'01, Notifications.
8.2 Airborne Protective Actions
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\\
8.2.1 Dose Assessment Steff Member or In plant Radiation Monitoring Technician, complete the Airborne Protec;ive Action Cuide Uorksheet (Appendix 12.2) as follows:
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\\
8.2.1.1 Obtaindistance(itemla),direcdionandaffected I
I downwind sector (item lb), expectei release duration (item 2), ground or elevated windspaed (item 3) and I
projected doses (item 10) f rom SP69 022.01, Decemination of Offsite Doses.
8.2.1.2 Using the distance (item la), the affected downwind sector (item Ib) along with the Protective Action Map (Appendix 12.5) determine the zone (item Ic).
- 8. 2.1. 3 Calculate the plume travel time (item 4).
8.2.1.4 Contact the Control Room and detemine the time the release started (item Sb) or the tice the release is expected to start (item Sg).
S.2.1.5 Enter the current time (item Se or item Sh) and complete the renaining items (either items 5d-e or 51-j) for the appropriate situation.
8.2.1.6 Determine the prevailing weather conditions and circle this in item 6.
Adverse weather consists of conditions which will significantly reduce traffic speeds, such as rain or light snow.
If severe weather (e.g., flooding or blizzard) conditions exist a separate evacuation time will have to be estimated.
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SP 69 026.01 Rev. 0 7/09/82 Page 3 J
8.2.1.7-Determine the evacuation time and record this in item 7.
The evacuation time is found by turning to the correct table of Appendix 12.3 for the prevailing weather
(
conditions (items 6a and 6b), Then with the affected downwind sector (itec lb), find the left most value that contains the zone (iteu Ic) and pick the evacuation time for either day or nigh ; (itec 6c) conditions.
8.2.1.8 Complete items 8 and 9 to determine the time a person evacuating will be exposed to the plume (evacuation exposure period).
8.2.1.9 If field monitoring teams are deployed near the area of concern, record the whole body dose rate and thyroid dose commitment values in item 11.
NOTE: Thyroid dose cot:itment is obtained by converting air sampler cps readings by use of SP69 023.01, Thyroid Dose Commitment using the TCS Sampler.
8.2.1.10 Determine most reliable projected dose (item 12) based upon reliability of field team ceasurements (if available). Record the projected. dose (item 12) on SPF69 022.01-2 Tabulated Dose and Protective Action Worksheet.
8.2.1.11 Cocplete items 13-15, and circle the higher recommended protective action for ite: 16.
Record these on the Tabulated Dose and Protective Action Worksheet
(
__.._._.SPF69.022.01-2.
8.2.1.12 Record the protective action on the Protective Action Map (Appendix 12.5).
8.2.1.13 Repeat this procedure for other distances used in SP69 022 01 Determination of Offsite Doses
.1 Consider recommending the same pr,otective action for adjacent zones.
.2 Consider reconnending the same protective action for adjacent zones as distanc: from the plant increases.
8.2.1.14 Af ter consultation with the Radiation Protection l
Manager / Radiological Control Manager (if available) give the completed worksheets (Appendix 12.5 and SPF 69 022.01-2) to the Energency Director / Response Manager for subsequent approval and transmission to offsite authoritier in accordance with SP69.009.01 Notifications.
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SP 69 026.01 Rev. O I
7/09/82 Page 4 i
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9.0 ACCEPTANCE CRITERIA
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N/A 10.0 FINAL CONDITIONS A protectiva action recommendation has been detercined and approved by the Emergency Director / Response Manager.
11.0 REFERENCES
11.1 Shoreham Nuclear Power Station Emergency Plan 11.2 SP69.022.01, Determination of Offsite Doses 11.3 SP69.024.01, Waterborne Release Dase Projection 11.4 SP69.023.01, Thyroid Dose Cocmit=ent using the TCS Air Sampler 11.5 SP69 009.01, Notifications 12.0 APPENDICES 12.1 Waterborne Protective Action Guidance Chart 12.2 Airborne Protective Action Guide '?orksheet, SPF69.026.01-1 12.3 Evacuation Times by Wind Direction 12.4 Shielding Factors from a Ga=ca Cloud Source 12.5 Thyroid and LThole Body Guidance Charts 12.6 Protective Action Map, SPF69.026.01-2
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SP 69 026.01 Rev. 0 7/09/82 Page 5
APPENDIX 12.1 Page 1 of 1
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WATERBORNE PROTECTIVE ACTION CUIDANCE CHART IF THEN Projected whole body or skin Instruct the U.S. Coas t Guard dose due to swimming is equal to remove all swinners within to or greater than 1 rem.
a 1 mile distcnce of the plant Projected whole body dose due Instruct the U.S. Coast Guard to boating is equal to or to evacuate all boats and greater than I rem.
vessels within a 1 mile distance of the plant I
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SP 69.026.01 Rev. 0 7/09/82 Page 6 l
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ -
Appendix 12.2
'Page 1 of 4 AIRBORNE PROTECTION ACTION GUIDE WORKSHEET 1.
Area of Concern a.
Distance miles (from SP69.022.01) b.
Direction degrees, Af fected Downwind Sector (from SP69.022.01) c.
Zone (A-S, from Appendix 12.6) 2.
Expected release duration hrs (from SP69 022.01) 3.
Windspeed miles /hr (from SP69.022.01)
NOTE: For ground releases use 33 ft. windspeed; for elevated releases use 150 ft.
windspeed.
item la/ item 3 4.
Plume travel time
/
hours
=
=
5.
Tice until exposure begins (choose a or f) a.
If release has begun:
b.
Time release has started (use 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> clock)
(
c.
Ti=e of calculation (use 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> clock) d.
Time difference = item Sc - item 5b =
hrs.
e.
Ti=e = item 4 - item 5d =
hrs.
NOTE:
If item Se is a negative nu ber, enter zero hours.
f.
If release will begin later:
g.
Time release is expected to start (use 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> clock) h.
Time of calculation (use 24 hr clock) 1.
Time difference = item 5g - item Sh =
hrs.
- j. Time = item 4 + item Si =
hrs.
SPF 69.026.01-1 Rev. 0
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SP 69 026.01 Rev. 0 7/09/82 Page 7
Appendix 12.2
.Page 2 of 4
(
6.
Weather condition and season (circle one for a,b and c):
a.
Ideal Adverse Severe b.
Seasonal Non-Seasonal c.
Day Night 7.
Evacuation time:
Use Appendix 12.3 along with information recorded in items 1 and 6 to determine the evacuation time. See procedure Step 8.2.1.7.
Evacuation time hrs.
8.
Exposure time item 7 - (item Sa og 5f)
=
=
hrs.
=
NOTE: If item 8 is negative, enter zero hours.
9.
Evacuation Exposure Period:
Smaller of item 8 ot; item 2:
hrs.
THYROID WHOLE BODY
(
10.
Projected Dose (fr,em_SP69 022.01) 10.
r em 10.
rem 11.
Measured dose from field monitoring teams (if applicable):
Monitoring Team Dose Rate X item 2 rem /hr WB x hrs.
11.
rem Thyroid Dose Commitment from TCS Air Sampler (froc SP69.023 01) 11.
(
SP 69.026.01 Rev. Q 7/09/82 Page 8
Appendix 12.2 Page 3 of 4
(
THYROID WHOLE BODY
- 12.
Most reliable projected dose 12.
rem 12.
rem (item 10 33; 11)
- 13.
Evacuation Dose item 9 x item 12/ item 2 x
/
(Thy.)
13.
__ /
(WB) 13.
rem x
- 14.
Shelter Dose Thyroid (a or b) a.
For item 2 less than or equal to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> item 12 x 0.33 =
x 0.33 b.
For item 2 greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> item 12 x (1 - 1.34) item 2
(
x (1 - 1.34) 14.
ren (a jg; b)
Whole Body item 12 x Structural Shielding Factor (Appendix 12.4) x 14.
(
SP 69.026.01 Rev. 0 7/09/32 Page 9
Appendix 12.2 Page 4 of 4
[
THYROID WHOLE BODY
- 15.
Refer to che Thyroid and Whole Body No Action No Action Guidance Charts (Appendix 12.5) and Circle the appropriate action for each Shelter Shelter Evacuate Evacuate
- 16.
Protective Action Recommendation (Circle One)
No Action Shelter Evacuate 17.
Indicate item 16 on the Protective Action Map (Appendix 12.6) for the affected zone I
(
SP 69 026.01 Rev.d 7/09/82 Page 10
^
^-
^
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EVACUATION Tlhicd BY WIND DIRECTION 3E/3SoNAL (IPtGit. c.os/D rsoA/s) 0-2P}i'LES 0-5 MILES O'10 MILES WEEK WEEK WEEK WEEK WEEK WEEK WIND DIFIECTION ZONE (8)
U.C JIGHT J _Y J O H T_
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~ WEEK ZONES
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~
(toward)
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DESIGN ATE ARE AS WITH RECOMMENDED
-Y ~
's J PROTECTIVE ACTION SYM00LS AS FOLLOW 5:
/
f Q
)k N-NO ACTION E-EVACUATE D
d I
S-SHELTER F-FOOD,W ATER & MILK CONTROL -
aoaicars o
O-OTHER(SPECIFY) b.7,
..c.,
s oou e.,
I u
. vfL-SP 69.026.01 Rev. 0 7/09/82 Page 17 i
' - 15 Su';sitted:
j M
&(
y I (m Reviewed /OQ ngr.:
Approved / Plant Mgr.:
d f
SP Number 69.023.01 Revision 9
Date Eff:
7/9/82 TPC TPC TPC 1
1 THYROID DOSE COMMITMENT USING TCS AIR SAMPLER
{
1.0 PURPOSE Ine purpose of this procedure is to obtain a thyroid dose commituent value from field teae survey results.
2.0 The Radiation Protection Manager / Radiological Control Manager is responsible for the implectentation of this procedure.
PPF 1921.600-6.421
(
3.0 DISCUSSION 3.1
{
This procedure is used to determine thyroid dose commitment from TCS air sampler measurements of airborne gross iodine samples taken by field survey teams.
3.2 Thyroid dose commitments is calculated by use of a nomogram once the following are known:
3.2.1 Filter / canister reading (cpm) 3.2.2 Bare canister reading -(cpm) 3.2.3 Background reading (cpm) 3.2.4 Time of reactor shutdown.(hrs) 3.2.5 Sample collection interval (min) 3.2.6 Duration of exposure (hrs) 3.2.7 Time of measurement (hrs) 3.2.8 Time of exposure (hrs) 3.3 Thyroid dose commitment is obtained from two components, gaseous and particulate iodine. In the accident case where core melt or fuel damage occurs, significant contribution from particulates exist. Particulate
(
contribution is obtained from the net filter / canister reading whi,le the gaseous contribution is obttined from the net bars canister reading.
4.0 PRECAUTIONS N/A 5.0 PREREQUISITES 5.1 An offsite radiological monitoring (ORM) team has been dispatched in accordance with SP 69.020.0,1, Downwind Surveys and air sampling with the TCS EAS-1 has been requested.
6.0 LIMITATIONS AND ACTIONS 6.1 Personnel using this procedure should be aware of the basis for the calculations and nomogram. Specifically:
6.1.1 The operation of the air sampler; including flow rates and sampling times.
6.1.2 Values required to be reported by the survey team to calculate thyroid dose commitment.
l
(
SP 69.023 01 Rev 0 07/09/82 Page 2
7.0 MATERIALS AND EQUIPMENT N/A
(
8.0 PROCEDURE 8.1 Dose Assessment Staff Member:,
8.1.1 When an offsite radiological monitoring (ORM) team reports field measurmments from the TCS EAS-1 Air sampler, all data listed on item 1 of the Thyroid Dose Commitment Worksheet (Appendix 12.1) is to be recorded.
8.1.2 Complete the remaining items on the thyroid worksheet as follows:
.1 Calculate sample collection interval (item 2), air sampler flow rate (item 3).
.2 Obtain net sample readings (items 4 and 5).
.3 Contact the control room to assess the possibility of core melt or fuel damage (item 6), determine the time of reactor shutdown (item 7), and determine the time the release started (item 9a).
.4 Calculate time between reactor shutdown and time of measurement (item 8), plume travel time (item 9b), time exposure started (item 9c), time after shutdown exposure started (item 10), and duration of exposure (item 11).
(
i-8.2 Dose Assessment Staff Member, using the Offsite Thyroid Dose Nomogram (Appendix 12.2) use the following steps to obtain thyroid dose commitment:
8.2.1 Bare Canister Component
.1 Locate the net bare canister iodine measurement (item 4) on the left hand axis. Move horizontally until the slanted line marked BARE CANISTER is intercepted.
.2 Move vertically up until the time between reactor shutdown and measurement (item 8) is intercepted; for time values greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, use the line marked I-131.
.3 Move horizontally to the right until the time between reactor shutdown and start of exposure (item 10) is intercepted; if the start of radiation exposure coincides with the time of measurement, move to the line marked Te = Tm.
.4 Move vertically down until the time between reactor shutdown and time of measurement (item 8) is intercepted;
(
SP 69.023.01 Rev 9 07/09/82 Page 3
if the start of radiation exposure coincides with the time of measurement, move to the line marked T'e,= Tg.
.5
. Hove horizontally to the right until duration of exposure (item 11) is intercepted.
Move vertica'lly up until the sample collection interval (item 2) is intercepted.
Move horizontally to the right to read off the thyroid dose commitment for the bare caniu:er. Record this in item 12.
8.2.2 Filter Component i
NOTE:
If core melt or fuel damage has not occurred, no iodine release in particulate form is expected and any filter radioactivity will be void of iodine (item 5 of Appendix 12.1 will be close to or equal to zero). The total dose commitment value (item 14) will be the bare canister component only. Otherwise, complete the steps below:
.1 Locate the net filter adsorber reading (item 5) on the lef t hand axis. Move horizontally until the slanted line corresponding to the number of hours between reactor shutdown and time of measurement (item 8) is intercepted.
.2 Move vertically up until the time between reactor
(
shutdown and measurement (item 8) is in;ercepted; for time values greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, use the line marked 1-131.
.3 Move horizonta2.ly to the right until the time between reactor shutdown and start of exposure (item 10) is intercepted; if the start of radiation exposure coincides with the time of measurement, move to the line marked Te = Tm.
.4 Movs vertically down until the time between reactor shutdown and time of measurement (item 8) is intercepted; if the start of radiation exposure coincides with the time of measurement, move to the line marked Te = Tm.
.5 Move horizontally to the right until duration of exposure (item 11) is intercepted.
.6 Move vertically up until the sample collection interval (item 2) is intercepted.
SP 69.023 01 Rev 0
[
07/09/82 Page 4 l
l
.7 Hove horizontally to the right to read off the thyroid dose commitment for the filter adsorber. Record this in item 13.
8.2.3 Total Dose Co=mitment
.1 Obtain total dose commitment by adding bare canister l
component (item 12) and the filter adsorber component (item 13). Record this value in item 14.
t
.2 Utilize results of survey data (if necessary) for input to SP 69 926 01 Protective Action Recommendations.
9.0 ACCEPTANCE CRITERIA
"~ -~
I i
N/A 10.0 FINAL CONDITIONS Thyroid dose commitment has been calculated.
11.0 REFERENCES
11.1 SP 69 020.01 Downwind Surveys 11.2 SP 69 026.01 Protective Action Recommendations 12.0 APPENDICES
(
12.1 Throid Dose Commitment Worksheet, SPF 69.023.01-1 2-12.2 TCS Air Sampler Offsite Thyroid Dose Nomogram 1
SP 69.023 01 Rev 9 07/09/82 Page 5
i
%ppendix 12.1 rage A or 4
(
THYROID DOSE COMMITMENT WORKSHEET 1.
Input from survey teams.
{
a.
Air sample i b.
Location miles c.
Canister F d.
Sample collection Start Time l
End Time L
e.
Flow Rate Start efa End cfm f.
Background reading cpm g.
Filter / canister epm h.
Bare canister reading epm 1.
Time of measurement (use 24 hr clock) 2.
Sample collection interval = difference between Start and End Time of item Id.
min
=
=
3.
Air sampler flow rate = average of Start and End Flow rate of item le.
(
+
) 2 '=
cfm I
=
(
4.
Net Bare Canister Reading - item lh - item If =
cpm
~~
5.
Net Filt er Adsorber Reading = item Ig - item lh =
cpm 6.
Has core melt or fuel damage occurred? (circle one) yes no 6
7.
Time of Reactor Shutdown date; time I
8.
Time between reactor shutdown and time of measurement = item 7 - li =
hrs 9.
Time exposure started:
i a.
Time release began:
date; time b.
Plume travel time = item Ib/ ground or elevated windapeed (mph)
/
jrs
=
c.
Time exposure started = item 9a + item 9b =
date; time 10.
Time after shutdown that exposure started
- item 9c - item 7 =
hrs 11.
Duration of radiation exposure hrs i
SPF 69.923 91-1 Rev 9 l
k SP 69.923.91 Rev 9 07/09/82 Page 6 t
,.,-..v..-
l l
. Appendix 12.1 Page 2 of 2 THYROID DOSE COMMITMENT WORKSHEET (Cont'd) 12.
Thyroid Dose Commitment due to bare canister component (based on Offsite' Thyroid Dose Nomogram)
Bare canister component =
rem.
13.
Thyroid Dose Commitment due to filter / canister component (based on offsite Thyroid Dose Nomogram)
NOTE: Filter /adsorber component for core melt or fuel damage only.
~~
Filter canister component =
zem.
14.
Total dose component - item 12 + item 13 =
ren I'.
I i
SPF 69 923 91-1 Rev 9 SP 69.923 91 Rev 9 07/09/82 Page 7 i
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.l Tabla 2.2 Protective Acrion Guidas for,Thryoid Dose Due to Inhalation.* rom a Passing Pluma i
I Projected Thyroid Dose j
Population at Risk res General population 5-25(*)
Emergency workers 125 i
Lifesaving activities (b)
I")When ranges are shown, the lowest value should be used if t
there are no major local constraints in providing protection at s
that level, sepecially to sensitive populations. Local con-strafal_ts may maka lom.r values impractical to use. but in no case snouin una nignet vaAus be excenaea 2n ueterm,ntng we need for protactive action.
(b)No specific upper 11mf t is given for thyroid exposura sinca in the arcrane. case complets thyroid loss might be' an
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accepwania penalty for a life saved. However, unis should not be necessary if respirators and/or thyroid protection for rescus personnel are available as the result of adequate pt - 4ag.
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1 Table 2.1 Protective Action Guides for Whole Body Exposure to Airborne Radioactive Materials l
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t Lifesaving activities 75 i
(
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(a)When ranges are shown, the lowest value should be used if
'v' there are no major local constraints in providing protection at that level, esperially to sensitive populations. Local con-straints may maka lower values impractical to use, but in no case should the higher value be exceeded in determining the need for protective action.
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PUBLIC PROTECTION STRATEGIES FOR POTENTIAL NUCLEAR REACTOR ACCIDDIT5:
1 SHELTERING CONCEPTS WITH EXISTING PUBlic AND PRIVATE STRUCTURES
- avid C. Aldrich, Ca rid M.. Iriesen, Jr., and Jay D. Jchnsen
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APPENDIX B Brick / Wood Housing Units Data concerning the percentage of brick housing units within each state was presented in the Reactor Safety Study [1] and is Figure Sk indicates graphically the percentages of repeated here.
family housing units that are brick for different parts of
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the country: the wide variation is conveniently categorized within' five regions. Data for this figure were derived from the 1970 Cansus of Housing
- and the 1971 FRA Homes, Data for States and 3
Selected Areas ** data. book published by the Deparment of Housing and Urban Development (HUD).
The HUD book gives statistics by state for existing single-f amily homes sold under the Federal Housing Administration (FEA),Section 203 program. These data show percentages of t; hose existing (used) houses sold that have br ic k', stone, or coner,ete-block exteriors. These percentages have been assumed to be typical of all single-family houses within the state.
The data were then adjusted to account for sultifamily structures, which were assumed to be of heavy construction (i.e.,
brick). By using the housing census data on sultifamily structures, the percentage of brick og equivalent housing units was estimated as follows:
,1 aultifamily units) + ( t single-f amily homes) (fraction that are brick)
(
As for the basement data in Appendiz C,' representativa per-contages of housing units that are brick wors estimated for seven geographic regions: Northeast, Great Lakes, Southwest, Midwest.
l Pacific Coast, Atlantic Coast and Southeast. The states l
6 comprising these regions are listed in Appendix C.
The j
'U.S. Copart=ent of Commerce, 1972, 1970 Census of Housine, cetailed
~
Bousino Characteristics, United States, Wasnington, 0.6.
- U.S. Department of Housing and Urbe.n Cevelopmant, 1972, 1971 FEA Homes. Data for States and Selected Areas.
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percentages for each state included withid a region (mid-values were assumed for the ranges in Figure 31), weighted by the number of housing units in that state, were averaged to entain the following regional percentages of brick housing units.
Region 4 brick,_hmusine units Northeast 47 l
Great Lakes 36 Southwest -
40 Midwest 35
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Pacific Coast 27 45 Atlantic Coast Southeast.
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APPENDIX C
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Basement Cata
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Basement data from the 1970 U.S.
Ecusing census
- is presented for each state in Table C1.
The total number of basements in each state was divided by the nunner of year-co,und housing units to estimate the percentage of homes with basements for that state.
As indicated, over 50% of U.'S. homes have a basement.
Also note that there is no correlation available betwesen basements and type of house construction'.
The percentages of homes with basements are typically similar for states within the same geographic area.
Basement data for individual states were combined to estimate representative
, percentages for seven geographic regions: Northeast, Creat Lakes,
(
Southwe st, Midwe st, Pacific Coast, Atlantic Ocast, and Southeast.
The total number of basements in each' region (i.e., the sum of the numbers for.each state in the region) was divided by the total number of year-cound housing units to estimate the percentage of homes with basements for that region. The states comprising each region, and the basSment percentages calculated are listed
~
below.
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2
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Oopartment of Commerce, 1972. 1970 Census of Reusine. Oetailed Housino Characteristics, United States, danning ton, 0.0.
t 19 h
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. em Recion
% homes with basements Northeast 87 (Connecticut, celaware, Maine, Maryland, Massachusetts, New Hampshir e,
New York, Pennsylvania, Rhode Island, Vermont and West Virginia )
Creat takes 77 i
(Illinois, Indiana, Michigan, Minnesota, Chio and Wisconsin) i Southwest 13
( Arizona, California, Nevada, New " Mexico, Cklahoma, Texas, Utah and Wyoming) f Midwest 71 1
(Colorado, Illino is, Ind'iana, Iowa, Kansas, Montana, Nebraska, North Dakota, South Oakota and Idano)
Pacific Coast 23 (California, Cregon and Wasnington) t Atlantic Coast 51 g
(Connecticut, Celaware, Florida, Georgia, Maine, Maryland,
)
Massachusetts, New Jersey, North Carolina, Rhode Island, South Carolina and Virginia)
, Southeast.
16 l
( Alabama, Arxansas. Florida, Georgia, Kentucky, Louisiana, f
Mississippi, North Carolina, Sout2. Carolina and Connessee)
.a O
e 5
l 11B12 C1. BAST 3 TENT DMA Flot 1970 U.S. SOE1HG CR2GtB Year-roural t hanes Year-rotsal 4 homme I,nustrwa imits Ba = ats
- w. baseeits twmstrua imits hmts v.l e t Alabama 1,114,845 160,677 14 Hontana 240,755
'155,521 65 Alaska 88,555 39,259 44 Whraska 511,473 405,688 19 Arizona 578,111 25,116 4
Hevala 111,658 23,412 14 213,815 C6
- Arkansas 672,961 52,260 8
k w ltispahlre 248,799
.1,915,056 83 California 6,916,261 1,170,214 17 kw Jersey 2,305,293 Colora)o 142,854 443,118 60 E w Natco 322,298 31,084 10 968,815 881,224 91 R w York 6,159,314 5,522,331 90 Conriecticut 114,990 112,113 64 mrth Carolina 1,619,548 381,055 24 Delaware Dist. of Qaluabla 218,390 233,146 84 Ikarth mkota 200,465 168,555 84 Flor ida 2,490,838 82,231 3
shio 3,441,860 2,621,202 76 morgia 1,466,681 304,81) 21 (klatuvaa 911,815 102.812 11 mwall 215,892 29,149 34 Oregon 135,631 265,211 36 IJain 238,293 130,456 55 Pennsylvania 3,880,102 3,466,494 89 Illirw>ls 3,692,441 2,854,269 7)
Iownle Islarmi 307,309 283,784 92 Irullena 1,711,896 999,320 58 fiouth Carolina 804,858 88,438 11 Iow.s 954,915 828,310 81 muth tbkota 221,636 170,102 11 gansas 781,508 435,365 55 honessee 1,291,000 368,153 28 i
gentucky 1,060,609 440,614 42 haas 3,809,086 131,486 4
foulelana 1,146,105 34,701 3
Utah 311,902 213,172 68 mine 339,440 280,264 83 veramt 149,162 121,761 85 Nrylarwl 1,234,680 930,061 15 Virginia 1,484,952 629,401 42 mssadiusetts 1,819,028 1,708,242 93 mshinjton 1,204,902 570,500 47 Hidalgan 2,845,448 2,204,469 78 Est Virginia 592.845 313,501 53 Hiruu: sot a 1,219,591 1,069,946 88 Wisansin 1,416,421 1,212,081 90 Hlasissigpl 691.211 35,103 5
thoaalaj 114,512 61,224 59 Hisa.ouri 1,665,536 1,094,080 66 t1 J. 'tutal 67,699,084 36,112,009 53 I
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