ML20134C594
| ML20134C594 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 07/30/1984 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Long J GENERAL ELECTRIC CO. |
| Shared Package | |
| ML20134B431 | List: |
| References | |
| FOIA-85-158 NUDOCS 8508160364 | |
| Download: ML20134C594 (273) | |
Text
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General Electric Company ATTN: Mr. J. A. Long, General Manager -
Wilmington Manufacturing Department P.O. Box 780 Wilmington, North Carolina 28402 Gentlemen:
SUBJECT:
SUMMARY
OF THE JULY 10, 1984 MEETING WITH GENERAL ELECTRIC This refers to the special meeting held at the Region II office on July 10, 1984, to discuss the denial by General Electric of a violation concerning statistical methods used to determine measurement control limits. The subjects discussed at this meeting and a list of the attendees are presented in the enclosed Meeting Summary and Attachment A, respectively.
It is our opinion that the meeting was beneficial and resulted in a better understanding of the issues. As discussed in a telephone conversation on July 24, 1984, between Mr. C. M. Vaughan of your staff and Mr. K. P. Barr of this office, we have reviewed the issues discussed in the July 10, 1984 meeting, and continue to believe that the violation did occur. You are hereby required to submit to this office, within 30 days of the date of this letter, a response in accordance with the Notice of Violation issued October 31, 1983.
In accordance with 10 CFR 2.790(d) ar.d 10 CFR 73.21, safeguards activities and security measures are exempt from public disclosure; therefore, Attachments B & C to the Enclosure to this letter will not be placed in NRC's Public Document Room.
The responses directed by this letter and the enclosures are not subject to the clearance procedures of the Office of Management and Budget issued under the Paperwork Reduction Act of 1980, PL 96-511.
Should you have any questions concerning this letter, please contact us.
Sincerely, l
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James P. O'Reilly ..'
Regional Administrator
Enclosure:
l Meeting Summary w/ Attachments '
(Exempt from Disclosure) cc w/encls: ./
C. M. Vaughan, Manager Licensing and Nuclear Materials Management Unit g 81 g 4 850621 RATNERBS-158 PDR t
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. l ENCLOSURE I MEETING
SUMMARY
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Licensee: General Electric Company Facility: Wilmington Manufacturing Department License No.: SNM-1097 Docket No.: 70-1113
SUBJECT:
STATISTICAL METHODS FOR CONTROL CHART LIMITS On July 10, 1984, representatives of the General Electric Company met with NRC Region II personnel to discuss the denial by General Electric of a violation concerning statistical methods used to calculate measurement control chart limits. The attendance list is attached as Appendix A to this Summary. The meeting was held at the request of the General Electric Company.
NRC representatives summarized the inspection findings, presented a review of the applicable requirements associated with statistical control systems, reviewed appropriate statistical -techniques described in recognized quality control textbooks, and sumrarized the General Electric statistical methods. NRC personnel also provided General Electric representatives with a verbal explanation of the review criteria which was used to approve all Fundamental Nuclear Material Control (FNMC) plans. A review of the General Electric FNMC plan revealed that the commitments contained in the plan were consistent with the NRC review criteria, but inconsistent with current General Electric practices.
General Electric representatives presented their justification for using their statistical control methods. A General Electric representative indicated that
- the commitments in the FNMC plan were not consistent with what General Electric had intended to convey, but that it was clear that General Electric's practices were not consistent with the FNMC Plan approved by the NRC. The NRC stated that if GE wanted to utilize such a technique, they should provide appropriate background. material to the NRC for proper review.
Copies of the visual aids used by General Electric and NRC in their July 10, 1984 presentation are attached as appendices B and C, respectively.
@c QQ .*_, , 7/ d 4 Briah L. Richards 1** Date Statistician Attachments:
A - Attendance List 8 - General Electric Visual Adis ,
C - NRC Visual Aid l
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ATTACHMENT A ATTENDANCE LIST Attendance at the General Electric - NRC meeting of July 10, 1984 at the NRC Region II Office was as foll<ws:
General Electric Company C. M. Vaughan, Manager, Licensing & Nuclear Materials Management R. I. Parnell, Control Programs Engineer W. Tucker, Statistician, Corporate R&D Center Nuclear Regulatory Commission K. P. Barr, Chief, Nuclear Materials Safety and Safeguards Branch, Division of Radiation Safety and Safeguards, Region II E. J. McAlpine, Chief, Material Control and Accountability Section, NMSS Branch C. N. Smith, Chief, Nuclear Materials Control Licensing Section, Fuel Facility Safeguards Licensing Branch, Division of Safeguards, NMSS
- 0. W. Jones, Statistician, Material Control and Accountability Section B. L. Richards, Statistician, Material Control and Accountability Section O
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ATTACHMENT B s-72 N -
Ob INSPECTION REPORT 70-113/83-28 Copy
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app Ti3kofII II NOTICE OF VIOLATION B l
10 CFR 70.57(b)(5) REQUIRES THE LICENSEE TO REVIEW AND APPROVE, BEFORE USE, WRITTEN PROCEDURES FOR ANALYZING PROGRAM DATA AND CONTROLLING MEASUREMENT PERFORMANCE.
IN ADDITION, 70.57(B)(10) REQUIRES THE LICENSEE TO ,
EVALUATE WITH APPROPRIATE STATISTICAL METHODS ALL PROGRAM DATA AND INFORMATION USED TO ESTABLISH PARAMETERS PERTAINING TO SPECIAL NUCLEAR MATERIALS CONTROL AND ACCOUNTING.
CONTRARY 'IO THE ABOVE, THE LICENSEE REVIEWED AND APPROVED PROCEDURE COI 5002, DATED MAY 6, 1983, WHICH DESCRIBES THE METHODS USED 'IO CALCULATE CONTROL CHART LIMITS FOR CONTROLLING MEASUREMENT PERFORMANCE, AND FAILED-TO DETECT THAT THE PROCEDURE CONTAINED THE USE OF INAPPROPRIATE STATISTICAL TECHNIQUES. THE SUBSEQUENT USE OF THIS PROCEDURE CAUSED THE LICENSEE TO CONTROL MEASUREMENT PERFORMANCE AT A LEVEL WHICH WAS INCONSISTENT WITH THE REQUIREMENTS OF 10 CFR 70.57(b)(11).
SEVERITY LEVEL: IV
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CMV 7/10/84
REGULATORY REFERENCES 10 CFR 70.57(b)(5):
(5) THE PROGRAM SHALL INCLUDE PROVISIONS FOR THE REVIEW AND APPROVAL, BEFORE USE, OF WRITTEN PROCEDURES FOR:
( i) PREPARING OR ACQUIRING, MAINTAINING, STORING AND USING REFERENCE STANDARDS ,
(ii) CALIBRATING MEASUREMENT SYSTEMS, PERFORMING BULK MEASUREMENTS, OBTAINING SAMPLES, AND PERFORMING COMPOSITIONAL ANALYSES, (iii) RECORDING, ANALYZING AND REPORTING THE PROGRAM DATA AND INFORMATION, AND (iv) CONTROLLING MEASUREMENT PERFORMANCE.
(10) THE LICENSEE SHALL EVALUATE WITH APPROPRIATE STATISTICAL METHODS ALL PROGRAM DATA AND INFORMATION, AND RELEVANT PROCESS DATA USED TO ESTABLISH BIAS CORRECTIONS AND THEIR ASSOCIATED UNCERTAINTIES, RANDOM ERROR VARIANCES, LIMITS FOR SYSTEMATIC ERROR, AND OTHER PARAMETERS PERTAINING TO SPECIAL NUCLEAR MATERIALS CONTROL AND ACCOUNTING MEASUREMENTS, AND TO CONTROL MEASUREMENT PERFORMANCE PURSUANT TO S 70.58( f) . BIAS CORRECTIONS SHALL BE MADE BY AN APPROPRIATE STATISTICAL PROCEDURE.
10 CPR 70.57(b)(11):
(11) THE LICENSEE SHALL ESTABLISH AND MAINTAIN A STATISTICAL CONTROL SYSTEM, INCLUDING CONTROL CHARTS AND
- FORMAL STATISTICAL PROCEDURES, DESIGNED TC MONITOR THE QUALITY OF EACH TYPE OF PROGRAM MEASUREMENT. CONTROL CHART LIMITS SHALL BE ESTABLISHED TO BE EQUIVALENT TO LEVELS OF SIGNIFICANCE OF 0.05 AND 0.001. WHENEVER CONTROL DATA EXCEED THE 0.05 CONTROL LIMITS, THE LICENSEE SHALL INVESTIGATE THE CONDITION AND TAKE CORRECTIVE ACTION IN A TIMELY MANNER. THE RESULTS OF THESE INVESTIGATIONS AND ACTIONS SHALL BE RECORDED.
WHENEVER THE CONTROL DATA EXCEED THE 0.001 CONTROL .
LIMITS, THE MEASUREMENT SYSTEM WHICH GENERATED THE DATA -
SHALL NOT BE USED FOR MATERIAL CONTROL AND ACCOUNTING PURPOSES UNTIL THE DEFICIENCY HAS BEEN BROUGHT INTO CONTROL AT THE 0.05 CONTROL LEVEL.
CMV 7/10/84
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3 GENERAL ELECTRIC'S POSITION 10 CFR 70.57(b)(5)
COI #002 REVIEWED BY APPROPRIATE & COMPETENT PERSONNEL COI #002 SUBSEQUENTLY REVIEWED INTERNALLY MOST RECENTLY REVIEWED BY GE-CR&D 10 CPR 70.57(b)(10)
SIMULTANEOUS STATISTICAL INFERENCE SIMPLE APPLICATION DERIVED FROM PROBABILITY THEORY RECOGNIZED IN LITERATURE 10 CPR 70.57(b)(11) i PROGRAM MEASUREMENTS CONTROLLED AT 0.05 AND 0.001 i
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SIMULTANEOUS STATISTICAL INFERENCE l I
PROBLEM TECHNICAL MISUNDERSTANDING l 1
PROCEDURAL CLARITY 1 CMV 7/10/84
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. 4 SIMPLE FORM SIMULTANEOUS STATISTICAL INFERENCB l CONTROL REQUIREMENTS MEASUREMENT QUALITY CONTROLLED SO THAT PROGRAM MEASUREMENTS ARE REPORTED AT THE 0.05 AND 0.001 SIGNIFICANCE LEVEL MEASUREMENT SEQUENCE SINGLE DETERMINATION OF STANDARD SEQUENCE OF PROGRAM MEASUREMENTS SINGLE DETERMINATION OF STANDARD DERIVATION OF CONTROL LIMITS Pr(PASS) = Pr(PASS 1st TEST & PASS 2nd TEST)
= Pr(PASS 1st TEST) Pr(PASS 2nd TEST)
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95, ALARM TWO SIDED LIMITS l
.999, OUT-OF-CONTROL TWO SIDED LIMITS )
IF .95 = X2 THEN X = .9746794
- i. EACH TAIL Pr = 0.0126603 l
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5 DICHROMATE TITRATION
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SIMPLE FORM MEASUREMENT SEQUENCE SINGLE DETERMINATION OF STANDARD SEQUENCE OF PROGRAM MEASUREMENTS SINGLE DETERMINATION OF STANDARD DICHTOMATE MEASUREMENT SEQUENCE SINGLE DETERMINATION OF NBS 950b SRM PROGRAM MEASUREMENTS (MAX 15 UNKNOWNS)
SINGLE DETERMINATION OF NBS 950b SRM DICHROMATE MEASUREMENT SEQUENCE IS THE SAME AS THE SIMPLE FORM EXAMPLE OF SIMULTANEOUS STATISTICAL INFERENCE O
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ATTACHMENT C CONTROL LIMI'TS FOR PPM IN RAD WASTE '
g __ _ _ . _ _ _ . .
(FFER .51 __- ___ .-_. - - . - _ - - - - - - - - - _ - - - - _ - - - - - - - - - - - - - - - - - - -_-i G N LIMIT __- _ _ - __ _ _ _ __ __ __ __ _ _ - __ __ __ __ __ __ . c 48 . _ . _ _- _ . _ _.- . _. .__ _ .. __ . _ . . _ . .,,
UPPER.85 N LIMIT as -
LOWER.55 ,
CONTLIMIT
.J_t = 25 ppm S=5.65 _ _ . . . . .
2s LDIER.N1 ~
N LIMIT c a
15 g tyg __ __ __
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a g - l G = General Electric method
- - M C = classical method
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WIUe*GTON MANUFACTURNG DipmATMENT 3 h -
GENERAL ELECTbC COMPANY + PO 90x 780 + WitMaNGTON, NORTH CAACXiNA 96409 g
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--. 84 November 15, 1984 Mr. James P. O' Reilly, Regional Administrator U.S. Nuclear Regulatory Commission, RII 101 Marietta Street, NW - Suite 2900 Atlanta, Georgia 30323
Dear Mr. O' Reilly :
References:
(1) NRC License SNM-1097, Docket 70-1113 (2) NRC Inspection Report 70-1113/84-11 dated 10/18/84 Thank you very much for your letter reporting the results of the inspection conducted at our licensed fuel fabrication plant by Mr.
B. L. Richards of your of fice on July 30 - August 2, 1984.
Pertaining to the items of apparent noncompliance with NRC regairements in your letter, the replies to these items are given in the attachment to this letter.
We appreciate your inspector's comments and sug'gestions related to our safeguards programs. These comments and suggestions are helpful to us in our constant efforts to maintain and, where necessary, improve these programs and to ensure the continuation of a successful safeguards effort at our plant.
We also welcome further discussion with your staff on the items in your letter and in our related replies, if necessary, for further clarification.
Pursuant to 10 CFR 2.790(d), General Electric Company requests that the attachment to this letter be withheld from public disclosure since this attachment identifies details of General Electric's control and accounting procedures for safeguarding licensed special nuclear material.
Very truly yours, GENERAL ELECTRIC COMPANY -
f Charles M.
kN- QlW Vaughan, Manager Licensing & Nuclear Materials Management M/C J-26
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GENERAL $ ELECTRIC CONTAINS 10 CFR 2.790(d) INFORMATION Mr. J. P. O' Reilly November 15, 1984 ATTACHMENT The information given below refers to the items in Enclosure 1 -
Notice of Violation, in the NRC Inspection Report 70-1113/84-11, dated 10/18/84.
- 1. License Condition 2.1 of Safeguards Amendment No.
MPP-3 to Special Nuclear Materials License No.
SNM-1097 requires the licensee to follow the current revision of their Fundamental Nuclear Material Control Plan. Section 6.6 of that plan requires the licensee to prepare and distribute DOE /NRC-741 nuclear material transaction reports in accordance with the pJblished instructions for the report. Tne published instructions, NUREG/BR-0006 requires the licensee to enter limits of error (954 confidence interval) on DOE /NRC-741 forms.
Contrary to the above, the licensee failed to
- correctly calculate limits of error which were entered on DOE /NRC-741 forms for shipments of uranium dioxide pellets. The licensee applied
< incorrect parameters to the limit of error esiculations which resulted in limits of error being reported that were not determined at the 954 confidence level.
Similar violations were disclosed during inspections conducted July 25-29, 1983 (reported in Inspection Report No. 70-1113/83- 21), and April 2-6, 1984 (reported in Inspection Report No. 70- 1113/84-06).
The licensee's corrective actions for these violations were not adequately implemented to prevent recurrence. This is a repeat violation.
This is a Severity Level V violation (Supplement .
III).
General Electric Company concurs with the above finding.
The incorrect Limit of Error (LE) occurred as a result of inaccurate sampling and measurement quantities used in the calculations.
s
- 2 GENERAL $ ELECTRIC CONTAINS 10 CFR 2.790(d) INFORMATION Mr. J. P. O' Reilly November 15, 1984 Attachment - Page 2 As we discussed at our September 6, 1984 meeting, GE's design I
philosophy for LE calculations was one of automating the work and integrating it into the near real time accountability system.
The use of automation typically eliminates the human error component that is responsibl a for inaccuracies in manual systems. At the time the original avstem and procedures were established, the shipping and receiving measurement plans were well defined and consistent time af ter time. We were successful in removing the human influence in the system design, however, in retrospect our degree of removal appears to have been too great.
Tr.e f i r s t two instances of LE inaccuracies were associated with receipts of materials. At that time we reviewed the entire program and identified what was the most probable root cause and took reasonable steps to correct it. The second situation was created by a sequence of human errors including a single individual who indicated they were not adequately. aware of the procedural change i which corrected potential problems associated with LE calculations
! on receipts of material.
i' Sometime after the initial violation in the sequence, changes were made in the type and sampling methodology of shipments of material.
2 This change invalidated one of the original principles of control philosophy applied to LE calculations and this fact was not l recognized by our routine change control program. This resulted in an error creating the third violation.
In order to prevent this type of incident from reoccuring, each category of receipts and shipments has been reviewed to determine if other similar conditions exist.
Provisions have been made to forward all documentation (such as certification and blend plans of shipments) that identifies the number of samples and analyses involved to the function responsible for performing the LE calculations. This will assure that the i information is obtained from source data and thereby reduce the i likelihood of error. The individuals involved with the subject )
calculations have been instructed by training sessions and by written documentation on how to check for and how to account for the 1
GENER AL & ELECTRIC CONTAINS 10 CFR 2.790(d) INFORMATION Mr. J. P. O'Reilly November 15, 1984 Attachment - Page 3 correct number of samples and analyses. Also, the internal procedure utilized in preparation of LE calculations for nuclear material shipments (L&NMMP 202) has been revised to incorporate these new controls.
Full compliance was achieved on October 24, 1984.
- 2. 10 CFR 70.57(b)(12) requires the licensee to establish a record system which allows for the efficient retrieval of program data. The licensee was notified by NMSS on May 14, 1984, that efficient retrieval meant retrieval within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for all measurement cont:01 data generated during the last 12 months.
Contrary to the above, as of August 10, 198', the licensee could not retrieve measurement control data associated with the. random analytical (isotopic) error calculation for uranium dioxide pellet shipments which was requested by the inspector on
! August 1, 1984. The data requested was generated by an agent of the licensee within the last 12 months.
This is a Severity Level V violation (Supplement III).
General Electric Company concurs with the above finding.
The measurement control records that were requested by the inspector could not be located because the datum involved was a new variance and documentation had not been established per the controlling internal procedure (P/P 140-5, Section 4.2.4.7) prior to its initial use. Typically a formal record, such as a Quality Notice (QN), is issued to establish documentation of new methods and variances. In this case, however, the procedure was not followed due to an .
oversight and the customary historic record did not exist. The work papers which would have also supported the values in use had been recently used and apparently misplaced or lost.
i
GENERAL $ ELECTRIC CONTAINS 10 CFR 2.790(d) INFORMATION Mr. J. P. O' Reilly November 15, 1984 Attachment - Page 4 The variance involved has been recalculated and documentation of the results are currently maintained in our files as work papers.
The function responsible for documenting variance calculations has reviewed the applicable procedure with their management to assure that this type of situation does not reoccur.
A formal record (in this case a ON) documenting the subject variance will be issued no later than 12/31/84.
- Full compliance will be achieved by December 31, 1984.
CM Vaughan
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%,*****+* O $ 0 $54 General Electric Company ATTN: Mr. J. A. Long, General Manager Wilmington Manufacturing Department P. O. Box 780 Wilmington, NC 28402 Gentlemen:
SUBJECT:
DOCKET NO. 70-1113 This acknowledges the receipt of your letters of February 14 and March 21, 1984, which transmitted revisions dated February 14 and March 21, 1984, to the Fundamental Nuclear Material Control Plan.
Our review of the changes has found portions cf the changes to be consistent with the provisions of 10 CFR 70.32(c). Other portions are not consistent with the provisions of 10 CFR 70.32(c) as delineated in the enclosure to this letter. To preclude a violation of regulatory requirements, you must not continue to imple-ment those changes deemed inconsistent. Please revert to the commitments in your previou:ly approved plan or, if desired, modify your plan to accommodate the enclosed comments and resubmit corrected plan pages as necessary to maintain plan continuity. Should you want to pursue those changes deemed inconsistent, you must submit a request to the Commission, Office of Nuclear Materials Safety and Safeguards under the provisions of 10 CFR 70.34 for amendment to your license.
It has been determined that your submittal contains information of a type spect-fied in 10 CFR 2.790(d). It is therefore deemed to be commercial or financial information within the meaning of 10 CFR 9.5(a)(4) and shall be subject to public disclosure only in accordance with the provisions of 10 CFR 9.12.
In accordance with Section 2.790(d) of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, activities involving safeguards and security measures are exempt from public disclosure; therefore, the enclosure will not be placed in the Public Document Room.
Should you have any questions concerning this letter, we will be glad to]iscuss them with you.
~
Sincerely, J. hilip o r, Director Division of Radiation Safety and Safeguards
Enclosure:
m/ _ , , ,a Inconsistent Changes O [ ygg Jy W J --/
(2.790(d) Information) cc w/er.:1: (See page 2) f 1 ,
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C. M. Vaughan, Manager Licensing and Nuclear Materials Management Unit l
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- 3. m :duced viithout specifte 3,, oval of IE:11 ENCLOSURE Inconsistent FNMC Plan Changes The following Fundamental Nuclear Material Control Plan change has been deter-mined to be inconsistent with the provisions of 70.32(c).
' Revision dated February 14,1984, Item 25, Section 4.9.2; replacing the word "will" with "may."
This change would not specifically address the tests required by 70.57(b)(9) for randomness and distribution for data used in error pooling.
i
' Revision dated February 14, 1984, Item 39 Table 7-2; restructuring the j acceptance criteria comparisons between shipper / receiver values.
This change eitminates the commitment to evaluate shipper receiver differences on a batch basis for element and isotope concentrations, this change would require an exemption from 10 CFR 70.58(g)(1).
1
' Revision dated February 14, 1984, Item 40, Section 7.10.3; restructuring' conditions for release of received SNM.
i This change which could allow would preclude SRDthe release of SNM prior to completion of sample analyses evaluation. .
i
' frequency Revision statement.
dated February 14, 1984, Item 46, Section C-1.3.1; deleting This change does not adequately specify the frequency of calibration error data collection. ,
' bration Revision dated February 14,1984, Item 48, Section C-2.2.1; revising cali-fraquency.
This change alpha significantly reduces the frequency of calibrations performed on counterst
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i General Electric Company ATTN: Mr. J. A. Long, General Manager Wilmington Manufacturing Department P. O. Box 780 Wilmington, NC 28402 Gentlemen:
SUBJECT:
03CKET NO. 70-1113 This acknowledges the receipt of your letters of February 14 and March 21, 1984, which transmitted a revision dated February 14 and March 21, 1984, to the Fundamental Nuclear Material Control Plan.
/
Our review of the changes has found portions of the changes to be consistent with l the previsions of 10 CFR 70.32(c). Other portions are not consistent with the provisions of 10 CFR 70.32(c) as delineated in the enclosure to this letter. To preclude a violation of regulatory requirements, you must not continue to imple-ment those changes deemed inconsistent. Please revert to the commitments in your previously approved plan or, if desired, modify your plan to accommodate the enclosed comments and resubmit corrected plan pages as necessary to maintain plan continuity.
Should you want to pursue those changes deemed inconsistent, you must submit a request to the Commission, Office of Nuclear Materials Safety and Safeguards under the provisions of 10 CFR 70.34 for amendment to your license. l It has been determined that your submittal contains information of a type spect-fied in 10 CFR 2.790(d). It is therefore deemed to be commercial or financial information within the meaning of 10 CFR 9.5(a)(4) and shall be subject to public disclosure only in accordance with the provisions of 10 CFR 9.12. '
In accordance with Section 2.790(d) of the hAC's " Rules of Practice," Part 2 Title 10, Code of Federal Regulations, activities involving safeguards and security measures are exempt from public disclosure; therefore, the enclosure will not be placed in the Public Document Room.
)
Should you have any questions concerning this letter, we will be glad to discuss them with you.
Sincerely, J.PhilipStohr,Dirhsctor Division of Radiation Safety and Safeguards
Enclosure:
Inconsistent Changes (2.790(d) Information) ,,
cc w/ encl: (See page 2) -
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, General Elcctric Company l -
cc w/ enc 1:
C. M. Vaughan, Manager I Licensing and Nuclear Materials I Management Unit bec w/ enc 1:
M4SS Docket Room, 70-1113, 396-55 Document Control Desk (RG02), 42-P Chief, Fuel Facility Safeguards Licensing Branch, 881-SS l Chief, Safeguards and Materials Program Branch, 359-EW Region II Licensing Flie, (R70X),
.(70-1113), TAB-B bec w/o enc 1:
License Fee Management Branch J. Kahle, Project Inspector l'
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_ ENCLOSURE Inconsistent FNMC Plan Changes The following Fundamental Nuclear Material Control Plan change has been deter-mined to be inconsistent with the provisions of 70.32(c).
- Revision dated February 14,1984, Item 25, Section 4.9.2; replacing the word "will" with "may."
This change would not specifically address the tests required by 70.57(b)(9) for randomness and distribution for data used in error pooling.
l
- Revision dated February 14, 1984, Item 39, Table 7-2; restructuring the acceptance criteria comparisons between shipper / receiver values.
This change eliminates the commitment to evaluate shipper-receiver differences on a batch basis for element and isotope concentrations, this change would require an exemption from 10 CFR 70.58(g)(1).
- Revision dated February 14, 1984, Item 40, Section 7.10.3; restructuring conditions for release of received SNM.
This change which could allow would preclude SRDthe release of SNM prior to completion of sample analyses evaluation.
- frequency Revision statement.
dated February 14, 1984, Item 46, Section C-1.3.1; deleting This change does not adequately specify the frequency of calibration error data collection.
- bration Revision dated February 14,1984, Item 48, Section C-2.2.1; revising cali-frequency.
This change falphacounte significantly reduces the frequency of calibrations performed on
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l General Electric Company ATTN: Mr. J. A. Long, General Manager Wilmington Manufacturing Department P. O. Box 780 Wilmington, NC 28402 Gentlemen:
SulWECT: DOCKET NO. 70-1113 This acknowledges the receipt of ycur letters of February 14 and March 21, 1984, which transmitted a revision dated February 14 and March 21, 1984, to the Fundamental Nuclear Material Control Plan.
Our review of the changes has found portions of the changes to be consistent with the provisions of 10 CFR 70.32(c). Other portions are not consistent with the provisions of 10 CFR 70.32(c) as delineated in the enclosure to this letter. To -
preclude a violation of regulatory requirements, you must not continue to imple-
~
ment those changes deemed inconsistent. Please revert to the commitments in your previously approved plan or, if desired, modify your plan to accommodate the enclosed comments and resubmit corrected plan pages as necessary to maintain plan continuity. Should you want to pursue those changes deemed inconsistent, you must submit a request to the Commission, Office of Nuclear Materials Safety and Safeguards under the provisions of 10 CFR 70.34 for amendment to your license.
' It has been determined that your submittal contains information of a type spect-fied in 10 CFR 2.790(d). It is therefore deemed to be commercial or financial information within the meaning of 10 CFR 9.S(a)(4) and shall be subject to public disclosure only in accordance with the provisions of 10 CFR 9.12.
In accordance with Section 2.790(d) of the NRC's " Rules of Practice," Part 2 Title 10, Code of Federal Regulations, activities involving safeguards and security measures are exempt from public disclosure; there fore, the enclosure will not be placed in the Public Document Room.
Should you have any questions concerning this letter, we will be glad to discuss them with you.
Sincerely, J. Philip Stohr, Director Division of Radiation Safety and Safeguards
Enclosure:
Inconsistent Changes (2.790(d) Information) ,
cc w/ encl: (See page 2) - m ammmmer
N t General E1cetric Company , 2 cc w/ enc 1:
C. M. Vaughan, Manager Licensing and Nuclear Materials Management Unit bec w/ enc 1:
18155 Docket Room, 70-1113, 396-55 Document Control Desk (RG02), 42-P Chief, Fuel Facility Safeguards Licensing Branch, 881-S5 Chief, Safeguards and Materials Program i Branch, 359-EW Region II Licensing File, (R70X),
(70-1113), TAB-8
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bec w/o encl- 1 License Fee Management Branch J. Kahle, Project Inspector l
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1 Pages h I Thio dscumnt 10 not to be
- reproduced without specific avroval of IE:II ENCLOSURE Inconsistent FNMC Plan Changes The following Fundamental Nuclear Material Control Plan change has been deter-mined to be inconsistent with the provisions of 70.32(c).
' Revision dated February 14, 1984, Item 25, Section 4.9.2; replacing the word "will" with "may."
This change would not specifically address the tests required by 70.57(b)(9) for randomness and distribution for data used in error pooling.
' Revision dated February 14, 1984, Item 39, Table 7-2; restructuring the . . .
acceptance criteria comparisons betvaen shipper / receiver values.
This change eliminates the commitment to evaluate shipper-receiver differences on a batch basis for element and isotope concentrations, this change would require an exemption from 10 CFR 70.58(g)(1).
' Revision dated February 14, 1984, Item 40, Section 7.10.3; restructuring conditions for release of received SNM.
This change could allow the release of SNM prior to completion of sample analyses which would preclude SRD evaluation.
' Revision dated February 14, 1984, Item 46, Section C-1.3.1; deleting frequency statement.
This change does not adequately specify the frequency of calibration error data collection.
- Revision dated February 14, 1984, Item 48, Section C-2.2.1; revising cali-bration frequency.
This change significantly reduces the frequency of calibrations performed on alpha counters.
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& . .i GENERAL ELECTRIC COMPANY WILMINGTON NANUFACTURING DEPARTMENT WILMINGTON, N.C.
RADIOLOGICAL CONTINGENCY .
AND l EMERGENCY PLAN JANUARY 18, 1982 O
N ,
- f N_ M p-3 125pp.
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TA"LE OF CONTENTS TITLE PAGE SECTION 1-1 1.0 GENERAL DESCRIPTION OF PLANT / LICENSED ACTIVITY Licensed Activity Description 1-1 l 1.1 Site and Facility Description 1-4 l 1.2 Products and Waste 1-13 1.3 Process Description 1-14 1.4 Radiological Material Containme.nt 1-20 1.5 ,
ENGINEERED PROVISIONS FOR ABNORMAL OPERATIONS 2-1 2.0 -
Criteria for Accommodation of Abnormal 2-2
! 2.1
Operations Process System 2-2 2.1.1 2.1.2 Alarm Systems and Release Prevention 2-4 2.1.3 Support Systems 2-5 2.1.4 Control Operations 2-8 2.2 Demonstration of Engineered Provisions For 2-9 Abnormal Operations 2.2.1 Process System 2-9 2.2.2 Alarm Systems and Release Prevention 2-16 2.2.3 Support Systems 2-27 2.2.4 Control Operations 2-36 3.0 CLASSES OF RADIOLOGICAL / EMERGENCY CONDITIONS 3-1 3.1 Classification System 3-1 i
i RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Page License SNM-1097 Date 2/25/85 Docket 70-1113 Revision 3 ;
TABLE OF CONTENTS SECTION TITLE PAGE 3.2 Recommended Classification Scheme 3-8 3.3 Range of Postulated Accidents 3-9 4.0 ORGANIIATIONAL CONTROL OF EMERGENCIES AND/OR 4-1 RADIOLOGICAL CONTINGENCIES 4.1 Normal Plant Organization 4-1 4.2 On-Site Emergency and Radiologihal' 4-3 Contingency Response Organization ,
4.3 Off-Site Assistance to the Facility. 4-6 "
4.4 Coordination with Participating Government'^ 4-10
- Agencies 5.0 EMERGENCY AND RADIOLOGICAL CONTINGENCY 5-1 MEASURES 5.1 Activation of Emergency Organization 5-1 )
5.2 Assessment Actions 5-2 5.3 Corrective Actions 5-4 5.4 Protective Actions 5-5 5.5 Exposure Control 5-11 6.0 EMERGENCY FACILITIES AND EQUIPMENT 6-1 6.1 Control Point 6-1 6.2 Communication Systems 6-2 6.3 Assessment Facilities 6-2 6.4 On-Site First Aid and Medical Facilities 6-4 2
RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Page License SNM-1097 Date 2/25/85 Docket 70-1113 Revision 3 . 11 -
TABLE OF CONTENTS TITLE PAGE SECTION Emergency Monitoring Equipment 6-4 6.5 Facilities Damace Control Equipment and 5-4 6.6 Facilities 7-1 7.0 MAINTENANCE OF RADIOLOGICAL AND EMERGENCY PREPAREDNESS CAPA8ILITY 7-1 7.1 Written Procedures Training 7-2 7.2 7-3 7.3 Test and Drills ,
Review and Updating of the Plan an'd'. Procedures 7-4
, 7.4 Maintenance and Inventory of Equipment and 7-5 7.5 Supplies 8-1 8.0 RECORDS AND REPORTS 8-1 8.1 Recordn of Incidents t
Records of Preparedness Assurance 9-1 8.2 8-2 8.3 Reporting Arrangement 9-1 9.0 RECOVERY 9-1 9.1 Reentry 9-2 9.2 Plant Restoration Resumption of Operations 9-3 9.3 10-1 10.0 APPENDICES RADIOLOGICAL COMTINGENCY & EMERGENCY PLAN Page License SNM-1097 Date 2/25/85
~
Docket 70-1113 Revision 3 - 111 -
LISTING OF FIGURES FIGURE TITLE PAGE 1.1 GE-NFMD Principal Buildings Arrangement 1-5
- 1.2 Plant Area Associated with Fuel Manuf acturina 1-6 Operations 1.3 Main Floor - Fuels Manufacturing Building 1-9
< 1.4 Mezzanine - Fuels Manufacturing Building 1-10 1.5 GE-NFMD Site Location 1-11
- 1.6 GE-NFMD Process Flow Sheet 1-15
- 2.1 Typical Air Sample Locations 2-13 __
2.2 GE-NFMD Criticality Warning System. Block .- 2-18
- Diagram 2.3 Criticality Warning System Detector Locations 2-19 FMO/FMOX 2.4 GE-NFMD Site Criticality Warning System 2-20 Detection Systems
)'
. 2.5 Typical Exhaust Air Cleaning System for 2-23 Uranium Processino Areas (Except for Wet Chemical Processing Area) 2.6 Exhaust Air Cleaning System for Wet Chemical 2-24 Processing Areas 2.7 Process Liquid Waste Treatnent 2-26 2.8 GE-Wilminaton Controlled Access Area 2-29 2.9 Details of Security Facility 2-30 2.10 GE-NFMD Plant Fire Protection System 2-34
- 2.11 Plant Fire Alarm Box Locations 2-37 8.1 Investigative Sequence 8-5 l
1 RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Page License SNM-1097 Date 2/25/85 Docket 70-1113 Revision 3
' ~ IV ~
1 LISTING OF TABLES TITLE PAGE TABLE 1.1 Twenty-Mile Radius Population Characteristics 1-12 2.1 Specific Facilities & Capabilities of 2-11 ,
ventilation Systems Radiation Detection Instrumentation 2-40 2.2 4-2
- 4.1 GE-NFMD Organization 4.2 Emercency Organization Structure 4-4 4.3 Plant Staff Emergency Assignments 4-7 5.1 Emergency Severity Classification 7 ' 5-6
' Notification & Responsibility Matrix 5.2 Emeroency Exposure Criteria 5-7 5.3 Summary of Immediate Protective Actions 5-9 7.1 Emergency Equipment Inspections 7-6 7.2 Initial Training and Periodic Retraining 7-7 9
i 8.1 Incident Classification 8-3 l
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RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Page License SNM-1097 Date 2/25/85 ~ ~
Docket 70-1113 -Revision 3 f
LISTING OF EXHIBITS
'T EXHIBIT TITLE PAGE 6.1 Emergency Control Center 6-5 6.2 Emergency Control Center Checkout SOP 6-6 6.3 Emergency Control Center Check 6-7 6.4 Emergency Cabinet Portable Instrumentation 6-8 6.5 Emergency Vehicle Inventory Checklist
- 6-9 7.1 General Electric Nuclear Fuel Men'ufacturina f-2
- Department Emergency Plan / Procedures Record of Concurrence ~
8.1.1 NFMD Emeraency Plan Report Summary ' Form 8-6
- 8.1.2 NFMD Emergency Plan Report Scenario Form 8-7 8.1.3 NFMD Emergency Plan Report Significant Events 8-8
- Sequence Form 8.1.4 NFMD Emergency Plan Report Attachments Form 8-9
- J 8.1.5 NFMD Emergency Plan Report Critique Summary 8-10
- Form RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Page License SNM-1097 Date 2/25/85 Docket 70-1113 Revision 3 - Vi ~
1.0 GENERAL DESCRIPTION OF PLANT / LICENSED ACTIVITY 1.1 Licensed Activity Description 1.1.1 License Number The Wilmington Manufacturing Department (WMD) of General Electric Company currently operates the nuclear fuel manufacturing plant in Wilmington, North Carolina, as a'uthorized by the U.S. Nuclear Regulatory Commission by License Number SNM-1097, Docket # 70-1113 issued January 13, 1969 and renewed on May 24, 1976. A License Renewal l
Application was submitted May 27, 1981.
1.1.2 Possession Limits The following types, quantities, and forms of special nuclear materials are authorized:
1.1.2.1 Uranium 235, 50,000 kqs total In any form, contained in uranium enriched to a maximum nominal equivalent of 44.
In the form of loaded fuel rods for use in f abricating fuel assemblies, contained in uranium to a maximum nominal enrichment of 4.54.
In the form of UO2 powder, for use in quantities of safe batches, in powder blending and in preparation of laboratory standards to be used in laboratory operations, contained in uranium to a maximum nominal enrichment of 6.04.
1.1.2.2 Uranium 235, 350 grams total In any form contained in uranium at any enrichment, for use in measurement, detection, and research or development.
Page-WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN 1-1 icense No. SNM-1097 Section No. I Ame nd . No . O Amend. Date 1/18/82 Amend. Section(s) _
l 1.1.2.3 Granium, 500 kes total In any form, contained in uranium at a maximum nominal enrichment of 154 for use in process technology development operations.
1.1.2.4 Plutonium 1 milligram and not more than 1.5 millicuries in samples for analytical purposes.
I milligram and not more than 65 mil 11 curies of.
~
plutonium-239, as standards for checking the response of radiation detection to alpha radiation. . . .
7 grams as sealed neutron sources <- 4 In nuclear fuel rods containing not more than 10-6 grams of plutonium per gram of U-235.
1.1.3 Authorized Activities 1.1.3.1 Product Processing Operations 1.1.3.1.1 UF6 Conversion - Conversion of uranium hexafluoride to [
uranium oxide powder.
1.1.3.1.2 Fuel Manufacture - Manufacture of nuclear reactor fuel rods and fuel assemblies using uranium oxide pellets fabricated from the uranium oxide powder and other non-uranium bearing ccaponents.
1.1.3.1.3 Scrap Recovery - Reprocessing of scrap from WMD and from other sources with nuclear safety characteristics identical to WMD in-process materials.
Pag.
WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN License No. SNM-1097 Section No. 1 Amend. No. O Amend. Date 1/18/82 Amend. Section(s) _l
1.1.3.2 Process Technology Operations 1.1.3.2.1 Conversion and fabrication of reactor fuel, fuel elements and fuel assemblies in small amounts or of advanced design.
1.1.3.2.2 Development of scrap recovery processes. ,
i 1.1.3.2.3 Ihstrument research and calibration, including development, calibration and functional testing of nuclear instrumentation and measuring devices using.
sealed plutonium-alpha-activated neutron sources.
~'
' 1.1.3.2.4 other process technology development' activities related ~
to, but not limited by, the above.
1.1.3.3 Laboratory operations Chemical, physical or metallurgical analysis and testing i
of uranium compounds and mixtures, including but not limited to, preparation of laboratory standards.
1.1.3.4 General Services Operations 1.1.3.4.1 Storage of unieradiated f uel assemblies, uranium compounds and mixtures in areas arranged specifically 1
for maintenance of criticality and radiological safety.
1.1.3.4.2 Design, fabrication and testing of uranium prototype processing equipment.
1.1.3.4.3 Maintenance and repair of uranium processing equip **nt and auxiliary systems.
Page WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Section No. 1 1-3 iconse No. SNM-1097 Amend. No. O Amend . Date 1/18/82 Amend. Section(s)
. . _ . - - _ _ _ _ . _ . _ --_. _ __ _ _ _ . _ _.~ _ _ - _ .__ .
1.1.3.4.4 Storage and nondestructive testing of fuel rods containing small amounts of plutonium.
1.1.3.5 waste Treatment and-Disposal 1.1.3.5.1 Treatment, disposal and/or shipment of liquid wastes whose discharges are regulated.
1.1.3.5.2 Decontamination of non-combustible contaminated wastes to reduce uranium contamination levels, and shipment of such low-level radioactive wastes to '1'icensed burial sites for disposal.
~
- e 1.1.3.5.3 Treatment or disposal of combustible waste and scrap material by incineration 1.1.3.6 Offsite Activities Non-destructive modification, testing, demonstration and storage of materials and devices containing unirradiated [
uranium, provided that such materials and devices shall be in General Electric's control at all times.
1.2 Site and Facility Description 1.2.1 Plant Layout and Material Use Locations l Uranium normally will only be used at the Wilmington site in the fuel manufacturing areas (see Figures 1.1 and 1.2).' Occasionally, but infrequently, small quantitites, i.e., less than one safe batch of uranium in a completely encapsulated form) may be used for special tests in other buildings or site locations. In ;
such cases, special preparations are made to prevent '
)
release of radioactive material to unrestricted areas.
Pag WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN
- i License No. SNM-1097 Section No. 1 Amend. Date 1/18/82 Amend. Section(s) _l
. Amend. No. O
FIGURE 1.1 GE-WMD PRINCIPAL BUILDINGS ARRANGEMENT 8
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Fuel Manufacturing Area
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FIGURE 1.2 PLANT AREA ASSOCIATED WITH FUEL MANUFACTURING OPERATIONS QWY .
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Pag WMD RADIOLOGICAL CONTINGENCY si EMERGENCY PLAN *'
License No. SNM-1097 Section No. 1 Amend. Section(s) l Amend. No. O Amend. Date 1/18/82 g- . . - - - - -- - ,, , ,y . , . --- ,.
For purposes of general orientation, the principal WMD buildings are described below.
1.2.1.1 Equipment Manufacturing Facility The Equipment Manufacturing Facility is a large steel, concrete and transite structure in which non-nuclear reactor components are manufactured.
1.2.1.2 Fuels Components Facility The Fuels Components Facility, a.,large building of similar construction to other Wilmington facilities, is used to manufacture non-nuclear (e.g. zirconium) --
components for reactor fuels.
1.2.1.3 Facility Maintenance Building This building is similar in construction to other buildings on the site and houses a centralized shop area utilized for maintenance, central stores, and related functions, none of which involve radioactive materials.
1.2.1.4 Fuel Manufacturing Facility This building is a structure fabricated of concrete block and insulated metal siding over a steel framework with a concrete floor. A built-up roof consists of a metal deck and insulation is topped with asphalt and gravel.
Connected to the south side of the Fuels Manufacturing Building is the chemical / metallurgical laboratory. The laboratory is constructed of tilt-up concrete slab siding with the same roof construction as that on the main building.
Pag WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Section No. I 1-7 License No. SNM-1097 Amend. No. O Amend. Date 1/18/82 Amend. Section(s)
i The Fuels Manufacturing Building and associated laboratory provide an integrated f acility for the processing of uranium compounds for the manuf acture of nuclear reactor fuels as more fully described in a later section. A general layout of the Fuels Manufacturing Building, including prime fuel manuf acturing process '
areas is shown in Figures 1.3 and 1.4. These figures show the controlled areas.
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1.2.1.5 warehouse Building A warehouse building, a pre-engineered structure with -
sheet metal siding, steel frame, and.a . poured concrete slab, is located north of the Fuels Manufacturing l Building. This building is used to store various nuclear fuel shipping containers - empty or full - as well as to store various non-nuclear items (industrial supplies, etc.).
I.
1.2.2 General Plant Location WMD is located approximately six miles north of A
Wilmington, NC.on U.S. Highway 117 (see Figure 1.5).
USGD 7.5' topographical map, Appendix B, demonstrates f
that GE-WMD is located in a rural area away from major 1
populated areas.
The map of the Wilmington, North Carolina metro area, Appendix I, identifies local routes of access, location of potential emergency facilities and other sites of potential emergency significance.
Pay WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN '-f Section No. 1 License No. SNM-1097 Amend. Date 1/18/82 Amend. Section(s) _
Amend . No . O
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FIGURE 1.3 MAIN FLOOR - FUELS MANUFACTURING BUILDING a .u .-
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Page' WMD RADIOLOGICAL CONTINGENCY f. EMERGENCY PLAN Section No. 1 1-9 iconse No. SNM-1097 Amend. No. O Amend. Date 1/18/82 Amend. Section(s) _
FIGURE 1.4 ME22ANINE - FUELS MANUFACTURING BUILDING
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WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN
Section No. t License No. SNM-1097 Amend. No. O Amend. Date 1/18/82 Amend. Section(s) l
FIGURE 1.5 GE-WMD SITE LOCATION l
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WMD RADIOLOGICAL CONTINGENCY f. EMERGENCY PLAN Section No. 1 1-1 icense No. SNM-1097 Amend. No. O Amend. Date 1/18/82 Amend. Section(s)
l 1.2.3 Depulation Distribution i The five-county area surrounding the plant site is essentially rural with a low population density. The population characteristics of the general plant area are listed in Table 1.1 4
TABLE 1.1 TWENTY-MILE RADIUS POPULATION CHARACTERISTICS Location from-Population Center 1980 Population Plant Site
~
Burgaw 2100 r- 16 miles north Carolina Beach 1791 20 miles south I
Castle Hayne 1500 3 miles north 4
Wilmington 44100 6 miles south Wrightsville Beach 2781 11 miles southeast 1.2.4 Site Neighbor Characteristics Most of the land within a five mile radius of the plant site is wooded and largely undeveloped. Localized developed areas are used for industrial, commercial, agricultural, residential, public, and recreation purposes. Three manufacturing plants are located within a six mile radius of the plant site the W. R. Grace &
Co. (ammonium nitrate fertilizer), Hercofina, Inc.
(chemical intermediates for the textile industry) and De Poortere Corporation's (pile f abrics) . Employment levels at these plants are approximately 200, 200, and Pag WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN
'-1 License No. SNM-1097 Section No. 1 l
Amend. No. O Amend. Date 1/18/82 Amend. Section(s) ,
l
1000 persons respectively. A small shopping center is located approximately three miles south of the plant site along U.S. 117. Within a five mile radius, several small commercial establishments are located along the area roadways.
With the exception of Castle Hayne (population 1500) to ihe north, residential development in the five mile area has been primarily in the form of single-family homes located intermittently along the area roads. Some small developments have started with a typical size range of 5 to 20 homes. There are a few churchys, one public ..
school, two private schools, and one' county prison facility.
The property immediately north of the site is primarily wooded, with limited residential development. The l property immediately south of the site is a lightly settled residential area with the majority of the area i being wooded or agricultural.
t 1.3 Products and Waste Products produced at WMD include (1) U02 fuel bundles comprised of sintered U02 fuel pellets, clad in zirealoy tubing and configured in a BWR fuel matrix, (2) sintered U02 pellets and (3) ceramic grade U02 powder, j
Waste generated are typical of this type facility and l
include (1) solid combustible and noncombustible trash,
! (2) fluoride liquid process waste, (3) nitrate liquid process waste, and (4) rad waste liquid and hydrofluoric j acid. l
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1 MMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Pagaj Section No. I 1-10 iconse No. SNM-1097 Amend. No. O Amend. Date 1/18/82 Amend. Section(s)
l l
1.4 Success Description !
taeluded in this section are descriptions of each major procese step. An overall process flow sheet is shown in Figure 1.8.
1.4.1 neceiving and Storing UFs Uranium hexafluoride (UF6 ) enriched in U-235 up to 4.04 il received in 2.5 ton, 30" diameter cylinders (Models OR-30A or OR-305) each contained within a protective shipping overpack (Models 11PF-1 and 2'1FF-2) .
~'
Storage space is provided for the sylinders on the elevated concrete platform adjacent to tne truck unloading area.
UF6 enriched in U-235 above 44 for use in the Process Technology Laboratory is received in 55 pound, $*
diameter cylinders (Model OR-SA), each contained within p a protective shipping overpack (Model 20PF-1). The e cylinders are stored in an area within the confines of the laboratory. -
1.4.2 UFa-to-Uo2 Conversion - ADO Process Cylinders are moved one at a time into the adjacent vaporisation room and lowered into cr.o of the vaporisation chambers. With the cylinder at amDient temperature, the valve cap is removed and flexible tubing is connected.
The cylinder is heated within its vaporization chamber by means of recirculation of air which is electrically heated within the closed' system. Vaporized UF6 flows Pag WMD RADIOLOGICAL CONTINGENCY a EMERGENCY PLAN License No. SNM-1097 Section No. 1 _
'-1 Amend. No. O Amend. Date 1/18/82 Amend. Section(s) ,
FIGURE 1.&
GE-WMD PROCESS FLOW SHEET
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1 1-1!
Amend. No. 0' Amend. Date 1/18/82- Amend. Section(s)
7 -- -
s 'M <Y j l through the installed header system and is hydrolysed to ,
00 F2 2 + UF in a hydrolysis vessel in the adjacent chemical processing room.
' When the proper concentration of uranyl fluoride (UO22 F) is formed, contents of the tank are fed by pump to a
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precipitation tank where the ammonia diuranate (ADU) precipitate is formed. Upon' completion of precipitation, the suspension is pumped to a d,igestor
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From the precipitation vesse1,,thecADU slurry is --
l continuously pumped to a dewatering . centrifuge.
Dewatered ADU " paste", containing about 50% water, is continuously fed into a gas-fired defluorination-reduction furnace where it is dried- rnd reduced to uranium dioxide (UO2 ). The UO2 powder is-discharged from the defluorinator and -1:s colle'eted in containers, <
weighed, and sent to the powder preparation operation.
1.4.3 UFg-UO2 Conversion - GECO Process A UF6 cylinder is placed in a steam autoclave and heated ,
by the condensing steam. The hot UF6 gas is fed to the '
re' actor where gaseous UF6, hydrogen and oxygen are 5.ntroduced to form U 03 8 and 002 which in turn is fed to e a defluorinator.
In the defluorinator, the powder is reduced to U02 which is sent to the powder preparation operation.
Pac WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN I r
License No. SNM-1097 Section No.
Amend. No. 0 . Amend. Date 1/18/82 Amend. Section(s)- '
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i 1.4.4 002 Powder Pre-Treatment Uranium dioxide discharged from the defluorinator is hammermilled, compacted and granulated.
1.4.5 Pellet Production 4 Containers of UO2 Powder are positioned one at a time in hoods which contain hoppers connected to tubes that feed U02 powder to the pellet presses on the. floor below.
Pellets formed by the pellet presses are nominally..a little more than 1/2" long and 1/2" in diameter and are transferred, as they are formed, into open-top box-
~
shaped molybedenum containers ( furnace boats) .
1.4.6 Sintering Furnace boats are are charged in a single line into one of five electrically fired furnaces. As the boats pass through the furnaces in a controlled reducing atmosphere, the pellets are sintered. Upon discharge from the furnaces, the furnace boats are stored on the slab-roller conveyor system prior to entering the next processing area which-is grinding.
1.4.7 Pellet Grinding Sintered pellets are processed through centerless grinders. Loaded trays of pellets are transferred via a
, cart to controlled storage cabinets.
T 1.4.8 Fuel Rod Loading Pellet trays are removed from the storage cabinets and transferred to rod loading stations where pellets are pushed into zircaloy tubes.
WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Pag Section No. 1-1
.icense No. SNM-1097 1 Amend. No. O Amend. Date 1/18/82 Amend. Section(s)
l 1.4.9 Fuel Bundle Assembly Fuel rods are scanned for U-235 content in an active scanner employing a neutron source and appropriate gamma radiation detectors.
Fuel rods are inserted into bundle spacer hardware according to a fixed insertion schedule. When all rods are in place, the assembly is raised to the vertical pos ition. '
1.4.10 Fuel Bundle Storage Following leak test and inspection;,, fuel bundles are __
stored in storage racks, suspended b'y the upper tie plate.
1.4.11 Packaging of Fuel Bundles for Transport Finished fuel bundles are removed by means of an overhead crane to the inner metal container of the GE Model RA-Series package. When loaded and sealed, the cover and end cap are bolted in place and the container is placed in the outer shipping container.
1.4.12 Scrap Recovery Internally-generated uranium compounds in various physical forms which do not meet quality standards, or which have been mixed with foreign material is reprocessed through scrap recovery equipment. This equipment is located in the UF6 to UO2 conversion area.
Recovered material is later blended with primary production flow at appropriate points in the process.
Pas l WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN '^
License No. SNM-1097 Section No. 1 i Amend. No. O Amend.'Date 1/18/82 Amend. Section(s) _
1.4.13 waste Treatment and Disposal 1.4.13.1 Liquid Radioactive Waste ( RADWASTE) System 1 waste water from sources such as laboratory sinks, l protective clothing laundering machines and area clean-up is routed to the RADWASTE system.
Concentration of uranium in water from these points dormally is quite low. The system consists of collection tanks, centrifuges and uranium monitoring equipment. Waste water is collected and then pumped to a dewatering centrifuge where sus'pe'nded uranium compounds and other solids are removed. The clarified ~~
water flows into a quarantine tanki sampled and pumped to the process waste disposal system. Higher-than-limits waste is returned to the system for rework.
1.4.13.2 Fluoride Waste Treatment Chemical wastes from the conversion process are collected in banks of slab tanks. When one tank system is filled the material is sampled and analyzed for uranium content. If the uranium content meets internal action guides, it is released to a large storage tank.
The liquid is then pumped from the storage tanks to a settling tank and the solid material is centrifuged out.
The supernate is treated with a lime slurry to accomplish recovery of the ammonia and removal of fluorides.
Af ter recovery of the ammonia, the liquid is pumped into storage lagoons in which solid CaF2 is allowed to settle. The liquid is sampled for uranium, nitrate, and l
Pag WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Section No. 1 1-1
.icense No. SNM-1097 Amend. No. O Amend. Date 1/18/82 Amend. Section(s) 1
l
- 1 ammonia content and fed into the plant industrial waste stream.
1.4.13.3 Liquid- Waste From the GECO Process The waste water from the GECO process originates in the defluorinator scrubber and the vacuum system. Both contain ammonium hydroxide and a small amount of The water from the defluorinator scrubber is fluoride.
pumped to a high ef ficiency filtration system -(inertial filtration) for recovery of uranium sElid's.
The waste water is sent to waste treatment where the solution is ~
pumped to a lagoon where the calciantfluoride precipitate is settled.
1.4.13.4 Solid Wastes Contaminated articles such as paper, rags, mops, plastic, wood, protective clothing, damaged tools, and equipment and similar contaminated materials which are i;
no longer serviceable are collected in designated containers to prevent the loss of contents and spread of contamination. Containers are located at points in the plant where such wastes may occur. These materials-are segregated into decontaminated noncombustible and combustible waste categories and disposed of by shipment to an authorized burial site or by incineration.
1.5 Radiological Material Containment 1.5.1 General Design Philosophy Design philosophy of'the GE-WMD nuclear fuel manufacturing facility, as it relates to containment of radiological material utilized in production, is based Pas WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN ' -
~
Section No. 1 _
l License No. SNM-1097 Amend. No. O Amend. Date 1/18/82 Amend. Section(s) I
upon (1) containment at the lowest operational levels, (2) source point monitoring, (3) timely detection capability, and (4) containment capability in event of a localized release.
1.5.2 Process System Design Considerations !
1.5.2.1 The process is the primary barrier of containment.
j 1.5.2.2 The next level of containment is the use of glove boxes, j
hoods, etc. to control airborne contamination if the l
process fails to contain the material.
s l ~~
1.5.2.3 Under design conditions personnel do:not require respiratory protection equipment 4
1.5.2.4 The ventilation system for the fuel manufacturing area supplies conditioned air and exhausts potentially contaminated air through filters.
1.5.2.5 Exhaust systems are designed to maintain a negative pressure in controlled areas relative to the outside environment.
I 1.5.2.6 The direction of air flow in the controlled area is from low contamination potential to the higher contamination l I
potential, i.e. exhaust ports are located in areas of highest potential airborne contamination.
l l
Pag!
WMD RADIOLOGICAL CONTINGENCY & EMERGENCY-PLAN Section No. 1 1-2:
.icense No. SNM-1097 Amend. No. O Amend. Date 1/18/82 Amend. Section(s) l
4 1.5.3 Rabaust Systems i
.Rabaust systems contain one final stage of HEPA filtration preceeded by other air cleaning devices specifically suited to the process steps served by the exhaust system, e.g. powder operations utilize pre-filters and primary HEPA filters and chemical processes utilize wet scrubbers.
1.5.4 Radioactive Release Detection '
1.5.4.1 Breach of Process Containment Controlled areas are continuously monitored by two independent air sampling systems; .one is a stationary sample system serviced by a central. vacuum facility; ~
another, more extensive , system utilizes on-line continuous sensors which read out in external areas.
1.5.4.2 Facility Exhaust Each exhaust system stack from uranium processing areas is sampled continuously at a point prior to discharge, i downstream of the final HEPA filter.
1.5.4.3 Liquid Effluent System Detection
- Each liquid waste stream containing uranium is-segregated from others. Within each process stream uranium content is measured prior to release.from one process step to another. A dam is provided as a final barrier / measurement point for liquid discharges to the Northeast Cape Fear River.
1 Pag WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN
'-2 License No. SNM-1097 Section No. 1 Amend. No. O Amend. Date 1/18/82 Amend. Section(s) ,
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2.0 ENGINEERED PROVISIONS FOR ABNORMAL OPERATIONS i
2.0.1 General Comments .
Nuclear fuel manufacturing at WMD involves a large scale, multi-step operation which requires rigorous process control and disciplined response to process perturbations. Detailed operational documents are in I place to describe response actions for out-of-control c'onditions and process perturbations which can be expected with any complex operation. In addition, as described in later Sections of th,.is., document, the WMD j Emergency Response Plan is structured to address all unusual incidents, ranging from relative insignificant abnormal conditions (e.g. , personnel ^. injury and equipment malfunction of a localized. nature)to significant abnormal conditions which require ~ activation ,
- of site emergency response teams.
1
) Engineered and administrative control systems in place to anticipate abnormal incidents are described in this section of the Plan. For clarification, specific criteria for performance of engineering systems for significant abnormal events, (i.e. require the l l
' activation of the site emergency response team) are i described in Section 2.1; demonstration information on 1 these systems is presented in Section 2.2. Section 2.2 i
also includes information related to engineered systems for handling abnormal events of lower' significance (i.e., handled by the local area management) and criteria for these systems are included in this Section rather than in Section 2.1. i 3
T Pago I WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Section No. 2 2-1' icense No. SNM-1097 Amend. No. O' Amend. Date 1/18/82 Amend. Section(s) o
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2.1 Criteria for Accommodation of Abnormal Operations 2.1.1 -process Systems 2.1.1.1 Criticality Warning System (CWS)
Outside system o 19 DA1-6CC Geiger-Mueller gamma detectors o 4 microprocessors i
Inside system o 27 DA1-6CC Geiger-Mueller gamma detectors o1 ionization detector (1-1000 r/hr). ' " ' '
o 6 microprocessors Alarm when 50 mr/hr above background +is. exceeded.
Evacuation alarm logic satisfied when two or more
' detectors in the same microprocessor exceed the high alarm set point or if one detector is in " fail" and another exceeds high alarm set point.
, . (
Sensors and their associated electronics are fail safe and designed to -operate when subject to intense radiation. ,
Alarm will continue after initiation until acknowledged.
System complies with Regulatory Guide 8.12,10 CFR 70.24
' and ANSI 8.3-1979 " Criticality Accident Alarm System".
Sensors placed to provide overlap with areas for i redundancy.
i i
l Pag l WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN
- -2 License No. SNM-1097 Section No. 2 f
Amend. No. O Amend. Date 1/18/82 Amend. Section(s) y
r l
l Daique audible alarm sounds through speakers placed throughout the building. Flashing red lights are
' also utilized in high noise areas.
2.1.1.2 Contrcl Area Monitoring Systems for Detection of Internal Uranium Releases l
' 2.1.1.2.1 Continuous Air Monitoring-System (CAM)
Approximately thirty units strategically placed in the control area.
Each unit is equipped with solid state detector and 4
single channel analyzer. .... .
Remote readout in Radiation Protection office and the 1
Emergency Control Center.
An airborne uranium release will result in an audible alarm when:
Trend: airborne uranium typically exceeds 3-54 of 10x10-Il uCi/cc limit Alert; when uranium airborne concentrations reach 50% high alarm limit 5x10-11 uCi/cc l High: when uranium airborne concentrations i
I reach 10x10-Il uCi/ce.
i System provides individual printouts for each CAM upon demand for 10 minute average over past four hour period l
and one hour average of past 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.
Page WMD RADIOLOGICAL CONTINGENCY 4' EMERGENCY PLAN Section No. 2 2-3 icense No. SNM-1097 Amend. No. O Amend. Date 1/18/82 Amend. Section( s)
S
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2.1.1.2.2 Stationary Air Sampler System (SAC) f 170 air samplers strategically placed throughout the l control areas.
Samplers attached to a central vacuum unit which has two separate electrical feeders and is a part of the emergency power system.
Samples analyzed for alpha activity in approximately 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> intervals.
~
Sample results in excess of 10x10-3:3'.uci/cc trigger response actions.
2.1.2 Alarm Systems and Release Prevention 2.1.2.1 Criticality alarm points discussed in section 2.1.1.1.
2.1.2.2 CAM alarm points discussed in section 2.1.1.2.1. ['
2.1.2.3 Fire alarm points discussed in section 2.1.3.4.
2.1.2.4 External Release 2.1.2.4.1 Stacks - All stacks for control areas are monitored.
Air sample filters changed weekly.
Results > 10x10-12 uCi/cc triggers response action.
2.1.2.4.2 Boundary External release from buildiing triggers downwind sampling as specified by Nuclear Safety Engineering and/or Environmental Protection Engineer.
Pag WMD RADIOLOGICAL' CONTINGENCY E EMERGENCY PLAN 'I
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License No. SNM-1097- Section No. 2 Amend . No . 'O Amend. Date 1/18/82- Amend. Section(s) f
t
. 2.1.2.4.3 Liquid waste Alert occurs when uranium content exceeds 20 ppm in treated waste process stream.
Dam is closed if liquid uranium level in normal effluent
> 5 ppa U or if a liquid spill occurs in drainage system of > 2 pounds of uranium.
2.1.3 Support Systems ;
2.1.3.1 Structural Performance vs Site Environmental Factors 2.1.3.1.1 Severe Natural Phenomena Building used to process and store radioactive materials
~
was designed to provide containment under adverse environmental conditions such as fire, wind,'~ flooding, earthquake.
Building is fabricated of concrete block, insulated metal siding over a steel framework with a concrete floor.
Roof consists of metal deck, insulation, and asphalt Covering.
Roof design is for 40-psi live-load in addition to dead load factor.
Earthquake loadings are per Vol. I " Uniform Building Code".
Page-WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN icense No. SNM-1097- Section No. 2 2-5f
' Amend. No. 0 Amend. Date 1/18/82- Amend. Section(s) l i
2.1.3.1.2 Accidents at Neighboring Activities Due to WMD's rural location, remote from other industrial, there are no foreseeable accidents that would adversely af fect WMD.
2.1.3.2 Confinement Barriers and Systems described in section 2.2.1.
2.1.3.3 Access and Egress of Operating ' Personnel and Emergency Response Teams The fuel manuf acturing f acility is constructed for quick emergency egress from the building,w..
Evacuation routes are maintained in a cleared position.
All buildings are within walking distance.
Emergency vehicles can be driven via existing roadways [
on site.
Major thoroughfares to the plant provide relatively easy .
I access.
2.1.3.3.1 Onsite Emergency personnel are issued an identification card or badge which authorize them access on or off the site during any emergency.
1 4
Pag WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN '
License No. SNM-1097' Section No. 2 .
Amend. No. O Amend. Date 1/18/82 Amend. Section(s) l
e-1 ,
4 2.1.3.3.2 Offsite '
Raternal support emergency personnel reporting to the security gate are escorted to the site of the emergency and directed to the senior person at the site. !
! 2.1.3.4 Fire and Explosion Resistance and Suppression l, The fire alarm pull box communication system reports to I a' central console located at the main plant gate.
Sprinkler system activated at temperatures of 165* to 212* F spraying water in approximately a 20' diameter.
~
Standard sprinklers with fusible link.
i
' Minimum water pressure on system is 90 pounds at all times.
i Halon systems used for fire control in compuger j
facilities.
i !
2 System has available water supply in excess of 600,000 gallons. ,
2.1.3.5 Shielding I The normal process and working conditions do not require 4
radiation shielding. The benefits of time and distance I are utilized by immediate evacuation af ter a criticality 4, accident.
i I
1 Page WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Section No. -
2 2-7 icense No. SNM-1097 Amend. No. O' Amend. Date 1/18/82 Amend. Section(s) i .
s 2.1.4 Control Operations
-2.1.4.1 anergency-Power 2.1.4.1.1 R1ectric 175-NP diesel operated generator delivers 115 volts to criticality alarm system, controlled area air sampling l
system, Emergency Control Center.
Activation when feed line A or B or both A & B voltage goes to zero. , ,
Equipped with voltage sensors and switching relay. ~
n-Full capacity will allow operation for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Additional fuel stored on plant site.
2.1.4.1.2 Battery Battery back up for criticality warning system allowing [
operations for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with no electrical power available.
Battery back up for autocall (fire alarm system) allows operation for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Battery operated emergency evacuation lights are placed throughout the buildings.
2.1.4.1.3 Remote Readouts for Radiation and -Fire are discussed in 2.2.4.
Pag WMD RADIOLOGICAL CONTINGENCY 'S EMERGENCY PLAN ^'
Section No. -
2-License No. SNM-1097-Amend. No. 0' Amend. Date 1/18/82- Amend. Section(s)
,- ..= - . - - - - - - - - - - - .-. . .. .. - - - - . _ _ . - . -
l
'2.2 Demonstration of Engineered Provisions for Abnormal l Operation
- 2.2.1 Process Systems
. 2.2.1.1 Containment The ventilation system for the fuel manufacturing areas I is designed to maintain a conditioned air supply to all I areas of the building and to exhaust potentially i c'ontaminated air through filters in containment devices and facility exhaust ports. Under design process conditions, personnel do not require.cespirato'ry ,
l I protection equipment.-
The process is the primary bar'rier oh containment for 5 the radioactive material and for other potentially dangerous substances during normal or abnormal i operations.
1 l
The primary process containment is supplemented with l glove boxes, hoods, transfer boxes, or other similar
! devices to control airborne contamination if the process i Containment designs for 4 fails to contain the material.
fuel manuf acturing areas include glove boxes, hoods, and ;
i l other special enclosures as applicable to contain
' airborne uranium'and thereby minimize personnel 1
exposures. ,
4 1
The design philosophy of primary and secondary '
containment systems shall be to prevent the release of uranium contamination to work areas during planned operation and to minimize it during: anticipated accident 4
conditions.
i Pag-WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN l 2-9
.icense No. SNM-1097 Section No. 2 f
Am.nd. No. o Amend. Dat. i/is/s2 Amend. S.ction(s) l
J
] gir flow through openings in these containment devices Nis measured periodically to assure adequate system .
performance as necessary for protection of personnel.
The survey is done at least monthly. When air flows through the openings do not meet minimum requirements of 80 LFPM at any point, action is in'stituted to correct the problem and restore containment to the minimum operating conditions. Additionally, the differential
~
pressure indicators across exhaust system filters are routinely checked to assure systim! performance. When a
- dif ferential pressure is observed to have reached four inches of water, the effectiveness _-.of the filter is -
investigated and if necessary the filter is-replaced to maintain the required air flow through openings and containment enclosures.
l 2.2.1.2 Specific Ventilation System Facil'ities and Capabilities
! Criteria for operation of ventilation system components [
is shown in Table 2.1 ,
i 2.2.1.3 Facility Air Monitoring Systems 4
l 2.2.1.3.1 Continuous Air Monitor (CAM) System 1
There are thirty-one CAM units used at WMD to identify airborne problems as they occur. Typical sensor locations are shcwn in Figure 2.1. These units are similar to the ones used in the central vacuum system with the additional features of a solid-state detector i and a single channel analyzer. The primary function of I
the CAM system is to provide early warning of loss of containment control.
a Pac WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN ~ '
l Section No. 2 i License No. SNM-1097-Amend. No. O Amend. Date 1/18/82 Amend. Section(s) l
. , _ . _ , - _ - . . ._ _ _ . . ~ _ . _ _ . _ _ _ . - . . _ _ _ __. _ _ _ _ _ _ _ _ _ , - _ - .
3LE 2.1
$ P- SPECIFIC FACILITIES & CAPABILITIES OF VENTILATION SYSTEMS e o a
a, o e
PURPOSE FACILITY ALAHMS, INTERLOCKS & SAFETY FEATURES I e
&zo Prevents carryout or
- Air flow designed > 80 lineal feet
- Hoods per minute.
~
blowout of radioactive E $ materials.
o x "
1 $ Fire extinguishers in work area.
Provides fire prevention.
g 4 o Prevents release of e o Effluent air filtered with absolute radioactive materials to O filters, E. environs.
> Prevents blowback or spread o e Glove Boxes < 1" HOAP 2 to working areas.
$ n a o z
d Effluent air filtered through Prevents release of q Q absolute filters.
contaminants to working i ; Q .
areas or environs.
D $ Provides fire prevention.
w < Fire extinguishers in work area and boxes where flammables are handled.
m
> m a Facilitates' cleanup.
3 g Smooth internal surfaces.
< u a a Air flow designated to maintain an Prevents spread of P' o' E High Velocity average of 200 lineal feet per ' radioactive materials f rom
,D Q Local Exhaust work area to immediate room e z minute. area.
0 0 "
- + M o' E Effluent air filtered with absolute Prevents release of u
filters.
radioactive materials in 8
2 environs.
Automatic hydrogen shutoff and Protects against hydrogen
" Sintering switch over to nitrogen with alarm explosion and resultant Furnaces signal.
spread of contamination as well as physical injury to, room occupants.
I u m O i
I-
t 4
32 ap
- m TABLE 2.1 (Continued) e PURPOSE E g FACILITY ALARMS, INTERLOCKS & SAFETY FEATURES Air flow designed > 125 lineal feet Provides cleanup of m $ Recirculating contaminated air within ,
j Air Systems per minute. rooms o
1 g Removes essentially all o o Air filtered in potentially
$ 3 contaminated zones with absolute. contaminants from room and fl r filters or water scrubbers. exhaust to environs.
p 8 I N Pressure drop indicator set to alarm Maintains adequate
" at < H2 0a P across final filter.
circulation for removal of '
i
, E ~ dust and contaminants from g Q the room air.
g j
s Controls temperature to not Temperature controller and alarm.
y exceed 300*F, which is 40*F 2
d 3a m UF6 vaporization below the temperature at
) $ Chambers which unsafe cylinder d
N pressure might be e generated. ,
[? Ventilation enclosure. Provides containment in e o w -
event of cylinder rupture
- 5. N. O
- ' ',f or abnormal leakage. i
@ $ t m 8 Electrically interlocked solenoiN . Prevents transfer of
$$ g valves between the cold traps and ' material to the UF6
[. * "$ ,
the hydrolysis tanks. cylinder from the
, g hydrolysis tank during
- , l operation of the cold trap
- systems.
n a
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l FIGURE 2.1 TYPICAL AIR SAMPLE LOCATIONS N
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E Stationary Air Samplers (168)
O Continuous Air Monitors (31)
! Pag WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Section No. 2 2-1
.icense No. SNM-1097 Amend. No. O Amend. Date 1/18/82 Amend. Section(s)
The CAMS, which are strategically located throughout the controlled areas, provide instant readout capability to the radiation protection function's office and the Emergency Control Center (ECC).
In the event of abnormal air concentrations, the system will produce three levels of alarms.
Trend Alarm - Produced when air concentrations are increasedabovepre-setpercentagesl(typically 3-5d).
Alert Alarm - Produced when the airborne. concentration exceeds a pre-set limit (typically 50% of the.high alarm limit).
High Alarm - Produced when the airborne concentration The high level exceeds twice the alert alarm limit. '
alarm is set at 10 x 10-11 uCi/cc. p In addition, there are individual printouts for each of the CAMS which. provide a ten minute average over a past four hour period and a one hour average over a past twenty-four hour period.
- 2. 2.1.3.2 Stationary Air Sampling System There are' currently two SAS systems in place in WMD.
The first is located in the FMO/FMOX area used in support of the existing ADU/GECO process. The second (new) system is located in FMOX and is used in support of the new GECO expansion process. Each system consists of a primary vacuum unit that supports a series of air sampling units.
Page WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Section No. 2 _
- 1 License No. SNM-1097 Amend. No. O Amend. Date 1/18/82 Amend. Section(s) l l
l
. - _ __. -..._. _ _._ _ _ ._. . _ _ _ . _ . _ . . _ _ _ _ . _ _ ~ . _
e i
~
.inne_ vacuum system has three levels of back-up to minimize the risk of downtime: a reserve vacuum pump for each area (total of four pumps); two separate electrical l l feeders (one for each active pump) coming from the i
substation each on a different transformers and a diesel generator to be used in the event of a total power loss.
A) proximately 170 stationary air samplers are used in j support of the ADU/GECO process and approximately 36 units will support the new GECO process. (See Figure i
2.1)
, g .
4 J
Each sampling unit has a flow meter that controls air i
volume and a filter holder containing a round glass 4
fiber filter (44 mm) which is changed every shif t.
These filter samples are analyzed'each shift for the i area's alpha activity within approximately four hours ,
I following removal from the filter holder. This analysis l
3 is performed by placing the filters into individual i
planchets and loading them into the low background alpha counting systems. The counting time requires j
j approximately one and a half hours.
4
,- 2.2.1.3.3 Portable 'Instrum(ntation 2.2.1.3.3.1 High Vblume Portable Units 1
i There are approximately eight high volume portable units ,
used at WMD for special spot sampling to determine airborne concentrations as required to evaluate breaches in containment and as back-up units during an emergency. ,
l These units maintain an air flow of about 20 cfm through a four inch ashless filter paper. The average run time 1 - ,
' Page -
WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Section No. 2 2-1
,icense No. SNM-1097 I
Amend. No. O Amend. Date 1/18/82 Amend. Section(s) i
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is between five and ten minutes. The units are self-contained inasmuch as they produce their own vacuum utilizing a 110 power source.
2.2.1.3.3.2 Low Volume Portable Units There are approximately six low volume portable units used at WMD for performing long-term airborne studies s'uch as determining airborne trends on new or existing pieces of equipment. These units maintain an air flow of 150 scfh through a 44 mm round glas's fiber filter.
2.2.2 Alarm Systems and Release Prevention-2.2.2.1 Criticality Warning System The WMD criticality warning system complies.with the requirements of Regulatory Guide 8.12. The criticality warning system can be divided into two systems. The outside system consists of 19 DA1-6CC Geiger-Mueller gamma detectors and four microprocessors (field units). [
The inside system contains 27 DA1-6CC detectors, one high-level ionization detector (1-1000 R/hr) model DA1-SCC, and six microprocessors (field units). The microprocessors continually poll the detectors for information, calculate dose rates, determine detector status, and maintain various history files. In addition, the microprocessors determine when the criticality alarm logic is satisfied and cause the evacuation alarms to sound.
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^l, Pag' WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN *1 Section No. 2 _
License No. SNM-1097 !
Amend. No. O Amend. Date 1/18/82 Amend. Section(s) _g l
( - -
A predetermined alarm point not to exceed 50 mr/hr above background is programmed for each detector. The evacuation alarm logic is satisfied when two or more detectors in the sa:.1 microprocessor exceed the high alarm set point or if one detector is in the fail status 1 and another in the same microprocessor exceeds the high l alarm set point. The system conforms to the r'equirements of 10 CFR 70.24.
Typical configurations of the criticality warning system showing a component block diagram and inside and outside detector locations are shown in Figures 2.2, 2,3,'and _
2.4. The detector locations and s[ stem configuration are subject to modification as may be' necessary to demonstrate adequacy of coverage. This det'ermination is made by the radiation safety function.
Each microprocessor is routinely polled by the central control terminals located in the radiation protection function office and the emergency control center and these terminals provide the system's current status using printouts and warning lights.
! The sensors and their associated electronics are fail-safe and are designed to initiate the prescribed alarm logic when' subject to intense radiation fields.
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Pag WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Section No. 2 2-1
.icense No. SNM-1097 Amend. No. O Amend. Date 1/18/82 Amend. Section(s) a
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FIGURE 2.2 l
GE-WND CRITICALITY WARNING SYSTEM BLOCK DIAGRAM neas r43 HI I * -
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FIGURE 2.3 j CRITICALITY WARNING SYSTEM DETECTOR LOCATIONS FMO/FMOX
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WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Section No. 2 2- 1' Icense No. SNM-1097 Amend. No. O Amend. Date 1/18/82 Amend. Section(s) l l
FIGURE 2.4 GE-MG SITE CRITICALITY WARNING SYSTEM DETECTOR LOCATIONS N' ..
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License No, SNM-1097 Section No. 2 -2' Amend. No. O Amend. Date 1/18/82 Amend. Section(s)
After initiation of the evacuation alarm, the
' audio / visual alarms will continue until acknowledged even though the radiation level falls below the alarm point.
The evacuation alarm system meets the guidance established in ANSI 8.3-1979 " Criticality Accident Alarm Iystem".
2.2.2.2 Facility Exhaust System The exhaust systems from uranium processing areas in the fuel manufacturing building are designed to maintain a ,_
negative pressure in controlled areas relative to the outside environment. This assures that air leakage is inward into the uranium processing areas. The negative pressure dif ferential is maintained by regulating the volume of fresh air taken by the ventilation system into the uranium processing areas.
All exhaust systems from the uranium processing areas are discharged:through high efficiency particulate air (HEPA) filter assemblies. Each exhaust system contains one final stage of HEPA filtration preceded by other air cleaning devices specifically suited to the process steps served by the exhaust systems. Some of these other air cleaning devices include profilters, primary REPA filters, and wet scrubbers.
These HEPA filters are at least 99.974 efficient for removal of 0.3 micron particles. At least one filter in each effluent air stream is equipped with a device for measuring differential pressure.
Pag WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN
,icense No. SNM-1097 Section No. 2 2-2 Amend. No. O Amend. Date 1/18/82 Amend. Section(s) 1
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rilter effectiveness is investigated when the pressure 'T differential across the filter exceeds four inches of water. A filter is replaced following evidence of damage to the filter or inability of the filter or the exhaust system to perform its function properly.
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Eachjof the exhaust system stacks, excepp'for the wet 1 ihemical process area andlthe incinerator, are serviced
- by an air cleaning system such as that>shown in, Figure 2'.5. Feed points to these stacks ~ include process areas 1 in which pellet pressing, pillet sintering, pellet grinding, rod loading, scrap sorting _ and '
decontamination as well as other operations-- f i
l
/ The exhaust systems from the chemical processing area which includes the process stens of vaporization, conversion, defluorination, ana uranium scrap recovery, are serviced by an air cleaning system which is depicted , {
e L .in Figure 2.6.
I t e 2.2.2.2.1 Source Point Moiitoringtof Airborne Effluents !
1 Each exhaust' system stack from.the uranium processing areas'is sampled continuously at a point prior to discharge and after the final HEPA filter in the system.
The stack air sampler continuously pulls a sample of air fromLthe'ilr stream in the stack through a filter. The filter on each sampler is changed and evaluated for l gross alpha activity _. The measurement of gross alpha
' activity from each stack air sampler filter is utilized to determine uranium concentration in the air and total uranium discharged from the stack.
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WMD RADICLOGICAJJ'ATINGENCY & EMERGENCY PLAN License No.'SNM-1097' Section No. >
2 ~M hmend. No. 0- Amend. Date 1/18/82- Amend. Section(s) ,
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FIGURE 2.5 TYPICAL EIBAUST AIR CLEANING SYSTEM FOR URANIUM PROCESSING AREAS
( EXCEPT ' FOR WET -CHEMICAL PROCESSING AREA)
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Secondary '
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Page WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN 2-2",
.icense No. SNM-1097 'Section No. 2 Amend. No. O Amend. Date 1/18/82 Amend. Section(s)
FIGURE 2.6 j
EXHAUST AIR CLEANING SYSTEM FOR WET CHEMICAL PROCESSING AREAS h h6
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Section No. 2 License No. SNM-1097' Amend. No. O Amend. Date 1/18/82 Amend. Section(s) g
The majority of the sample filters are changed on a weekly basis. The sample filters on the stacks contributing the larger portion of the total activity released are changed on a daily basis.
2.2.2.2.2 Action Level for Airborne Effluents Data from the air sampling measurements are entered into a computer program and are analyzed for comparison with the concentrations established as an internal action guide. The occurrence of an individual stack value exceeding the internal action guide will initiate review action. .
2.2.2.3 Liquid Effluents The liquid waste streams containing uranium from the fuel manufacturing operations are kept segregated as nitrate wastes, fluoride wastes a'nd radiation waste.
This separation makes it possible t.) utilize final individual treatment processes most compatible with the specific streams.
Each of these separated streams is processed through a quarantine tank system before it is released from the fuel manufacturing operation. The quarantine tank control system assures that internal guidelines for uranium concentrations are met before the liquids are released from the building to the final treatment processes.
Figure 2.7 shows schematically how each of the waste streams is treated before impoundment or release.
Page WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Section No. 2 2-2
,1 cense No. SNM-1097 Amend. No. O Amend. Date 1/18/82 Amend. Section(s)
FIGURE 2.7 PROCESS LIQUID WASTE TREATMENT musW>3 on
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Amend. No. O l
1
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The das provides an impoundment point when the potential exists for a liquid release to the environment, if levels reach 5 ppe in normal effluent, or if a liquid I spill occurs containing 2 pounds of uranium.
2.2.2.3.1 Source Point Monitoring 'of Liquid -Ef fluents (Water)
All process waste liquids are collected, treated and
("with the exception of nitrate wastes) discharged to
' the Northeast Cape Fear River via the discharge canal.
i Figure 2.7 details the treated processseffluent flows from the site. This figure also shows the final discharge measurement points. .. ..
2.2.3 Support Systems 2.2.3.1 Structural Performance versus Site Environmental Factors 2.2.3.1.1 Severe Natural Phenomena Design of the WMD f acility was performed by J.E. Sirrine Co., Greenville, N.C. in accordance with existing local, i state, federal and national codes, standards and/or regulations. The building and appurtances used to
- process and store hazardous materials were designed to provide for containment of such materials under extreme uncontrollable environmental conditions such as temperature, fire, wind, flooding, and earthquake.
i 2.2.3.1.2 Accidents'at Neighboring Activities i
Because the GE-WMD plant is located in a rural environment, removed from other industries, there is no i
accident foreseeable at any local industry which could adversely affect activities at GE WMD.
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Page WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Section No. -
2 2-2'
.icense No. SNM-1097 Amend. No. 0- Amend. Date 1/18/82 Amend. Section(s) ._
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r 2.2.3.2 Confinement Barriers and Systems 2.2.3.2.1 CAA Isolation Barrier The Control Access Area (CAA) security fence shown in Figure 2.8 is constructed of number 9 gauge fencing.
ThisCAAperdgeterfencingissubstantialenoughto deter the casual passerby from unauthorized penetration and to isolate the SNM. The CAA perimeter barrier channels all entry and exit for personnel and vehicles through established security control points. .
2.2.3.2.2 CAA-Access / Egress Control Personnel and vehicle traffic control wr y. to
. c and from the CAA is provided at access points in the CAA yerimeter barrier. A security facility within the Emergency Control Center (ECC) building is located at the primary employee access control point. Figure 2.8 shows the location of the ECC and Figure 2.9 shows the security
' facility within the ECC. The security facility is continuously manned by members of the security force, who monitor access and egress of personnel and vehicles.
Other access points are either similarly manned by security force personnel or they are closed and secured.
2.2.3.2.2.1 Personnel-Access Authorized personnel gain access to the CAA by passing through the pedestrian breezeway beside the security facility. Personnel badges are checked by the security force as personnel enter and exit the breezeway. A system of uniquely numbered, color-coded badges is used at Wilmington to identify employees and other persons authorized routine access to the site and CAA facilities. __
Pa$
WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Section No. 2 ~?
License No. SNM-1097 Amend. No. O Amend. Date 1/18/82- Amend. Section(s) g l
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FIGURE 2.8 GE WILMINGTON CONTROLLED ACCESS AREA
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I Pag WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Section No. 2 2-2.
.icense No. SNM-1097 Amend. No. O Amend. Date 1/18/82 Amend. Section(s)
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FIGUP.E 2.9
.. A ;, DETAILS OF SECURITY ~ FACILITY
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i License No. SNM-1097 Amend. No. O Amend. Date 1/18/82- Amend. Section(s) l l
l _
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certain color configurations on picture badges identify types of employees (hourly or salaried) and certain l contractors, while various categories of non-picture badges identify visitors, vendors and other contractors. l Documented procedures are in place to assure proper f
)
badge issuance.
2.2.3.2.2.i Vehicle Access Vehicle access to the CAA is limited to those required by operational necessity. Employ'ee's private vehicles are not authorized access to the CAA except for unusual circumstances on a case-by-case basis. Drivers and vehicle occupants are checked for possession of as valid badge authorizing admission and are logged in by the watchman at the security facility.
2.2.3.3 Access and Egress of Operating-Personnel and Emergency Response Teams 2.2.3.3.1 on-Site A description for evacuation to the normal staging area or to a remote staging area is provided in Section 5.4.1. Emergency response team re-entry techniques .are defined in implementing Emergency Procedures.
I 2.2.3.3.2 Near Site 4 Offsite evacuation can be accomplished through the local Civil Preparedness Agency (see Section 4.4.5). The offsite based emergency personnel who may have a need to respond to emergencies at GE-WMD are identified in Section 4.3. .
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WMD RADIOLOGICAL CONTINGENCY & EMERGENCY-PLAN Section No. 2 2~
.icense No. SNM-1097-Amend. No. O Amend. Date 1/18/82- Amend. Section(s)
J l
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The main north-south Highway (117) has no major i obstacles (bridges, railways, etc.) that would prevent f access or egress from GE-WMD during an emergency.
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2.2.3.4 Fire and Explosion Resistance and Suppression
)
A schematic of the GE-WMD fire protection system, a description of the fire protection program, aand fire safety considerations are presented in the previous section.
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- No special provisions for explosion suppression or
- resistance are utilized at GE-WMD..gy~ --
2.2.3.4.1 Fuel Manufacturing Building _
~~
The building is f abricated of concrete block and insulated metal siding over a steel framework with a concrete floor. A built-up roof consists of a metal deck and insulation which is topped with asphalt and gravel. The insulated steel deck and roof construction
,j meets Factory Mutual requirements for minimum fire hazard and wind resistance. It is designed for 40-psi live-load in addition to the dead-load f actor.
' Earthquake loading and design criteria are based on'the ,
applicable portion of Volume I, " Uniform Building Code",
latest edition. The building is complete sprinklered except for the U02 powder storage area and the chemical process control room, and is equipped with hose connections. Water is supplied from onsite wells which feed a 300,000 gallon elevated water storage tanks and ;
j I a grade level reservoir of the same capacity. The f acility and processes have been insured for nuclear liability and property coverage by the American Nuclear :
Paq WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN ' -
~
Section No. 2 _
License No. SNM-1097' Amend. No. O Amend. Date 1/18/82- Amend. Section(s) l I
f Insurer (ANI). Routine audits of all facilities included in the nuclear risk insurance pool, Figure ,
are performed by the insurer. ;
4 2.2.3.4.2 Fire' Protection System Components The fire protection system is designed in accordance with the National Fire Prorection Association standards.
Prime components of the fire protection system (Figure 2.10) are: ,
1,000 gpm diesel pump with automatic startup -
capabilities for supplying the fire protection loop from the retentien basin with water at-125 psi.
Electric jockey pump to maintain a 90 lb. pressure
' at all times on the fire protection system.
A 10" cast iron underground fire main loop around the prime production facilities.
r A series of underground branch headers - normally 8" - from the 10" main loop supplying fire protection water to sectionalized sprinkler systems in each productton building.
A supervised alarm and warning system (autocall) l
! providing 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> coverage of prime fire protection safety auxiliaries such as sprinkler system supply l
valve closing, water flow in sprinkler system, fire pump operations, smoke detector operation, etc.
Pag ;
WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Section No.. 2 _
2-2 sicense No. SNM-1097 Amend. No. O Amend. Date _1/18/82 Amend. Section(s)
I
FIGURE 2.10 GE-WMD' PLANT FIRE PROTECTION' SYSTEM J
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'-2 Section No. 2 License No. SNM-1097 Amend. No. 0- Amend. Date 1/18/82 Amend. Section(s) f i
Fire extinguishers designed for specific fire j control utilization and strategically located for l primary fire containment. l l
Fire hose on reels connected to the primary fire protection system.
Halon systems for primary fire control in computer facilities. ,
Hose test and certification facility.
Smoke detectors in essential exhaust systems.
' An emergency vehicle with extra hose, protective clothing, self-contained breathing apparatus and miscellaneous tools and equipment.
The fire protection system is supplied by the fifteen site deep wells having a system capacity of approximately 1,125 gpm.
2.2.3.5 Shielding Ventilation, containments, and the process equipment provide shielding to prevent internal exposure to radioactive materials such as uranium. In the event of a criticality accident, immsdiate evacuation uses time and distance as the technique to limit exposure from radiation.
Pag WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Section No. -
2 2-3
.icense No. SNM-1097 Amend. No. O Amend. Date 1/18/82 Amend. Section(s) i l
__.________________________________.________________________________.._________________________.__n.__________________________________._____..________________________
2.2.4 Contr.o1 operations 2.2.4.1 Besote Instrumentation Monitoring 2.2.4.1.1 Remote Radiation Status Readouts The computer console in the Radiation Protection office
]
provides readouts for radiation levels, airborne concentrations in the area and stack alarms (ches north 1
and chen south).
The computer console in the Emergency Control Center provides similar readouts to the" Emergency Organization.
The Radiation Protection office has 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> -
survelliance. .--
2.2.4.1.2 Remote Fire Signal Alarm / Readout The computer console in the security office gate one provides local alarm.and readout for the following conditions: '
r (1) fire alarm box pulled (Figure 2.11 shows no. &
location of box)
(2) sprinkler system activated (3) criticality alarm on pads or in building activated Security maintains a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> surveillance system.
2.2.4.2 Fire Protection Monitoring Routine inspection and testing of the fire protection system is conducted by security personnel under the direction of the manager of the industrial safety function. Maintenance and operation of the fire Pat WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN
- Section No. -
2 License No. SNM-1097 Amend. No. -0* Amend. Date 1/18/82- Amend. Section(s) _,
_ _ . _ , y . .
l FIGURE 2.11 PLANT' FIRE ALARM BOX LOCATIONS h . .. . .
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2 2-3; sicense No. SNM-1097 Amend. No. O Amer.d. Date 1/18/82 Amend. Section(s)
.i i
j protection system and equipment is the responsibility of I
the manager of the installation engineering and the site i
services function.
i 2.2.4.3 Emergency Power l Process equipment design provides for fail-safe l
l conditions should electrical service be interrupted.
i'mergency power is provided for water supply, supervised f alarm system, and essential equipment cooling. . . The i ;
following are emergency power applidations-i i
2.2.4.3.1 Emergency Lighting - Individual Unitacin Area i
' Battery operated emergency lighting to provide safe i egress from all interior building locations. .4-8 hour t
,I duration.
2.2.4.3.2 Emergency Power - Autocall System Main ' Guard Shelter l F ;
Provides automatic switch over of autocall system to f batteries to maintain surveillance of supervised alarm ,
l system throughout the plant. Duration 4-8 hours.
i
- 2.2.4.3.3 Emergency Power - Criticality System - Emergency control I
l Center l Provides automatic switch over to battery systesa to l
provide continuous criticality surveillance until system l '
is automatically transferred to the emergency generator.
I
- ?
2.2.4.3.4 Emergency-Power - FMo Critical System l
A 175-HP diesel-operated generator, located outside the east end of the fuel manufacturing building, provides an automatic startup of the emergency generator and a f switch over to the emergency system in the event of a '
t 1 Pag f WMD RADIOLOGICAL CONTINGENCY s-EMERGENCY PLAN '-3 I Section No.
- 2 _
l License No. SNM-1097 Amend. Date 1/18/82 Amend. Section(s) !
) Amend. No. O 4
l l
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power failure. Emergency power is provided for the criticality alarm system, the controlled area air
- sampling system, and the sintering furnace cooling system.
4 2.2.4.4 Radiation Detection Instrumentation Appropriate radiation detection instruments are a"vailable to ensure adequate radiation surveillance can ,
f Selection criteria of-portable and be accomplished.
laboratory counting equipment is. based.,on the types of radiations detected, maintenance requirements, ruggedness, interchangeability and upper and lower ,,
I limits of detection capabiliti'es. ~ A' detailed listing of the types of radiation detection instruments employed at WMD is shown in Table 2.2. The radiation safety function annually reviews'the types of instruments being used for each monitoring function and makes appropriate
) recommendations.
Emergency Equipment Storage and Maintenance l
2.2.4.5 j
Counting equipment is stored and made available for
- routine use at various plant locations such as the j
tadiation protection offices, designated locations and controlled area change rooms. Emergency equipment is j
} also stored and made available in the-radiation i
protection offices and designated emergnecy lockers. 1 l Additional emergency counting and survey equipment are 4 ]
available in the site emergency control center. i
)
l Maintenance is provided at specified frequencies by an I ' assigned equipment maintenance function, by the l
manufacturer's representative, or by contracted service vendors.
Pag i WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Section No. 2 2-3 j
.icense No. SNM-1097 l
, Amend. No. O Amend. Date 1/18/82' Amend. Section(s) l l
l 4
i l
TABLE 2.2 ;
RADIATION DETECTION INSTRUMENTATION I Typical Range Routine Use ;
g Dose Rate Meters GM Low Range 0.01mR-200mR Area Dose Rate Survey 0.0 5mR- 10 00 R Emergency GM High Range -Monitoring Ion Chamber Low Range O .1mR-10 R Area Dose _
Rate Surveys ;
Shipment Survey 1mR-1000R Emergency' High Range Monitoring Alpha Survey 50 cpm- Direct Personnel
' 2x10 6cpm & Equip. Surveys Neuton Meters 0.5 Rem-5 Rem Special Dose Rate i
Surveys' l Laboratory Instrumentation Multichannel Analyzer N/A Lab Analysis Lab Analysis Automatic Air .N/ A Sample Counter Lab Analysis i Windowless Gas-Flow N/A Proportional Counter Fixed Geometry N/A Lab Analysis Geiger-Mueller Counter N/A Lab Analysis Sodium Iodide Well
! Counter N/A Lab Analysis Phoswich Detectors N/A Lab Analysis Beta Surface Barrier Detectors )
i.
Pai
' WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN ' -
Section No. 2 License No. SNM-1097-Amend. Date 1/18/82- Amend. Section(s) _,
l Amend. No. O
l 1
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3.0 CLASSES OF RADIOLOGICAL / EMERGENCY CONDITIONS 3.1 Classification System Emergency conditions are classified into categories covering a broad spectrum of probable and possible emergencies. Criteria are specified for recognizing, characterizing and declaring each emergency Planning is classification, or sub-class as applicable.
coordinated with State and local agencies to ensure that the system is compatible with their systems. The system provides for appropriate notification'6f authorities for implementation of immediately applicable action and for -
upgrading the response to the appropriate classification level in the event of a chang + in the severity of the condition.
The classification scheme is outlined in Sections 3.l~.1 through 3.1.4. A summary of the emergency classifications is presented in Table 3.1.
3.1.1 Unusual Event 3.1.1.1 Personnel Emergency This emergency classification is characterized by any on-site occurrence in which emergency assistance for one or more individuals is required. It includes those situations that have no potential for escalation to more severe emergency conditions and which ara unlikely to cause an alteration of plant operating status. An unusual event (personnel emergency) does not activate the entire emergency organization. but may activate teams such as the first aid team or the plant medical unit. The scope of' situations applicable to this Pag, WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN 3-1 Section No. 3
'icense
. No. SNM-1097 Amend. No. O Amend. Date 1/18/82 . Amend. Section(s) _
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classification extends from minor first aid treatment of i
a single individual through severe injuries to several individuals requiring treatment at off-site medical facilities. Situations in this class may or may not 4
involve radioactive contamination or significant radiation exposure. The Wilmington Plant Safety Manual and other normal operating procedures provide for specific personnel emergency actions. They also establish g'uidelines to ensure that the severity of an injury and the extent of radioactive dont' amination -
and/or radiation exposure is recognized. -
j .-
3.1.1.2 Local Plant Emergency Occurrences within this Plant Emergency classification r
are local in nature involving relatively few personnel and/or a relatively small area of the plant. In these
' cases, the plant emergency (local) would be handled by the Building Manager and the building emergency teams. 'l The necessary response may be evacuation of individuals from only a local area within the plant while the local perturbation is brought under control. Applicable evacuation measures shall be conducted in accordance
' with Section 5.4.1 of this Plan.
The categories Airborne Radioactivity Concentration in i
contro11ed' Areas and spill of Radioactive Material in most cases involve relatively few personnel and can be controlled to minimize potential consequences. Typical examples of response include evacuation from a local area within a plant building due to a sudden increase in airborne radioactivity or radioactive contamination level in that area. )
Pa WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN ~ I Section No. 3 _
License No. SNM-1097 Amend. Date 1/18/82 Amend. Section(s) _
Amend. No. O
, .- . . _ - . - - - _ _ - _ _ - ~- .. _ . ._ - . _
The categories Fire, Explosion and Toxic Material Release are potential emergency occurrences at any major industrial facility. The initial response by personnel is evacuation from the affected area and activation of normal emergency teams (e.g. fire fighting) but additonal consideration and precautions may be required due to potential complications involving radioactive daterial.
Provision is made for activation of the Site Emergency organizations in the event that a cond'ition in the Local Plant subclass becomes of such magnitude as to be "'
1 escalated to the Operational Plant Emergency subclass of the Plant Emergency Classificaiton.
3.1.2 Alert 3.1.2.1 Emergency Alert This classification involves situations which could lead to identified hazard potentials. The situation has not yet caused damage to the facility nor harm to personnel and does not necessarily require an immediate change in facility operating status. Inherently, this is a situation in which time is available to take precautionary steps and/or mitigate consequences.
Emergency. alert conditions imply a rapid transition to a state of readiness by the facility personnel and possibly by off-site emergency support organizations, the possible cessation of certain routine non-essential functions or activities within the facility and possible precautionary actions that a specific situation may require. Situations placed in this classification are Pag WMD RADIOLOGICAL CONTINGENCY 6 EMERGENCY PLAN Section No. 3 3-3;
,1 cense No. SNM-1097 Amend. Date 1/18/82 Amend. Section(s) _
l Amend. No. O 1
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t threats to or breaches of plant security measures, and severe natural phenomena in the plant environment.
Specific candidates for Emergency Alerts are bomb threats, civil disturbance, confrontation, intrusion or severe weather. Initial recognition of such events may be from external sources, such as warning of severe weather or security threat.
f Although procedures and facility desigh features minimize the probability that an event in this "'
classification would result in a severe real emergency condition, provision is made for escalation to the appropriate level for any condition covered in this classification.
Notification to and from off-site agencies for alerting to a situation within this classification is made when ('
required. (See Appendix B) 3.1.2.2 Operational Plant Emergency
' When the emergency condition is, or becomes, severe enough to represent a hazard to a major portion of a plant operation and/or to a significant number of individuals, the incident is identified as an operational Plant Emergency and a higher level of response is provided. Major plant areas may be evacuated. Site support functions are marshalled to be available if needed.
P a<
WMD RADIOLOGICAL CONTINGENCY 6 EMERGENCY PLAN Section Nd. 3 License No. SNM-1097 Amend. Date 1/18/82 Amend. Section(s) _g Amend. No. 0
- t e
motification of off-site organisations may be a ;
requirement for conditions which comprise an Operational Plant Emergency.
iO Escalation to a site Emergency shall be implemented in the event that consideration of protective measures for off-site individuals is warranted, or at the discretion of the Emergency Director.
l The criteria for recognizing Operational Plant '
Emergencies are as follows: ,
~~
I o Airborne Radioactivity Concentration in Controlled Areas - Continuous air monitors or air sample f analysis indicate abnormal airborne radioactivity 7
j concentrations requiring special precautions for j
personnel protection in a large area of the plant.
i i
o Radioactive Airborne Ef fluent - An effluent monitor or the analysis of an ef fluent sample indicates an '
l airborne release of radioactive materials which j - !
l could result in concentrations in uncontrolled areas in excess of the applicable exposure limit for that area.
l o Spill of Radioactive Material - A significant spill -
1 of radioactive material occurs in a normally clear ,
l area or requires evacuation of personnel from plant buildings or areas.
l I o Liquid Effluent - A liquid effluent monitor or the analysis of an effluent sample indicates release of Pat .
WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN l Section No. 3 3-!'
- icense No. SNM-1097 l Amend. Section(s)
! Amend. No. O Amend. Date 1/19/82
. - _ .- ~ ~ _ , - - . - . , - . . _ _-_.-,--_y--,---,_e_- % . - . - __ .m~, ---.-.--. ,. ,- -
.,-v-
i radioactive material in uncontrolled areas in excess of the applicable concentration limit for that area. t o Fire - A fire detection instrument alarms or a fire is reported. The fire may or may not be of a l
magnitude or in a location which has the potential '
9 for causing the release of radioactive materials.
o Explosion - An explosion occurs which damages plant ~
equipment with or without inj diy' 'to' personnel .
i I o Toxic Material - A toxic material. is released within the plant which remains in the plant but in such
{ concentrations to be immediately hasardous to plant employees and which may ultimately af fect the off-
] site Population.
[
3.1.3 Site Emergency This classification includes those accidents that could I result in releases of radioactive and/or toxic materials t to the environment of sufficient magnitude to warrant consideration of protective measures for off-site
! individuals. Although such an uncontrolled release is [
not expected to occur during the life of the plant, provisions are made t.o ensure the readiness of plant '
i personnel and off-site emergency organizations.
i Additional criteria for recognizing and declaring a l
condition as a Site Emergency are as follows:
i Fire or Explosion - A fire or explosion of such l l
magnitude and location as to (1) cause a hazard to a i
Pat WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN -
Section No. -
3 -
License No. SNM-1097 0- Amend. Date 1/18/02 ' Amend. Section(s)
Amend. No.
1
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l major site facility, (2) jeopardise the safety of plant personnel, or (3) cause the major release of radioactive material off-site.
Criticality - A criticality alarm activated by the s
sensors for outside locations and sensors throughout the fuel manuf acturing building. -
l 1
I The Emergency Control Center will normally be the primary area for coordination of site emergency J measures.
~~
1 Evacuation and assembly of on-siterpersonnel shall be in accordance with section 5.4.
3.1.4 General Emergency l
This classification encompasses hypothetical accidents which have been postulated as having the potential for radiological exposure consequences to health and safety 1 of the surrounding communities.
Postulated accidents at the Wilmington Manufacturing i Department having the greatest potential for off-site l
radiological impact would be the release of all the UF6 (4800 lbs.) f rom a shipping container stored outside,
)
- or a criticality excursion. Neither of these have a ,
I reasonable potential for serious radiological l consequences to health and safety of the surrounding l
communities. Therefore emergency action levels and i I
other criteria for declaring a General Emergency are not included in the GE-WMD Radiological Contingency Plan.
l '
i Detailed evaluation of accidents having potential for i
Paq j WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Section No. 3 3-7
'1 cense No. SNM-1097 Amend. No. O Amend. Date 1/18/82 Amend. Section(s) l l
! I l
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of f-eite impact are set forth in Section 5 of I anvironmental Report, NEDO-20197, Class 1, January 1974, .
l General Electric Nuclear Facility, Wilmington, North Carolina.
Table 3.1 EMERGENCY CLASSIFICATION
SUMMARY
NRC Classification GE-yMD Classification Unusual Event Periennel Emergency- ,
Local Plant Emergency Alert Emergency Alert .-
Site Emergency Site Emirgency, General Emergency General Emergency" 3.2 Recommended Classification Scheme WMD employed the NRC. recommended system as defined in the previous section (3.1). Implementing procedures which cover emergencies and classification include an f emergency description, initiating signal, emergency personnel work stations, identification of specific responsible individuals, an action sequence overview and communication requirements. These documents are supplemented by detailed functional procedures and instructions for identified ' individuals in the emergency organization to provide them with action sequences in a step-by-step logical sequence, sufficiently detailed for a qualified individual to perform the required activities.
Pag WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN License No. SNM-1097 Section No. 3 Amend. No. 0 Amend. Date 1/18/82 Amend. Section(s)
(
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I i Bahibits provided in Appendix J are representative Laplementing documents which represent key postulated accidents including the coordination summary and the Emergency Director's instructions.
3.3 Range of Postulated Accidents This section of the Radiological Contingency Plan describes how postulated accidents are encompassed within the emergency classifications, provides a summary analysis of their implications for' emergency plann'ing, including (1) assessment of off-site impact, (2) instrumentation capability for detection and continued --
assessment, and (3) manpower needs in relation to the anticipated sequence and timing of events.
The inanpower needs for taking immediate action to minimize damage to the plant and' equipment, and to initiate protective measures on-site and off-site are provided by the normal shift operating crew. The composition of this around-the-clock crew is shown in Table 4.3. Emergency assignments for those individuals and for augmenting emergency support personnel are described in Sections 4.2 and 4.3.
3.3.1 Fire and Explosion The postulated accident of an explosion in a calciner in the FMO facility will result in the release of uranium compounds. They would most likely remain inside the building unless there is a simultaneous failure of the ventilation filtering systems then a portion of these uranium compounds could be released to the environment.
Building personnel immediately aware of the occurrence f
WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Paq
.icense No. SNM-1097 Section No. 3 3-i-
/
Amend. Section(s)
Amend. No. O Amend. Date 1/18/82
- r -
will activate the nearest fire alarm box which directs
.the Fire Brigade to the scene of the incident. (See Appendix B).
The Building Manager or the Emergency Director will direct recovery actions, depending on the severity of the event. Assessment of the potential for off-site Eelease will be made by the Emergency Director for major fires and explosions.' Data for the ,as,,s' essa'ent' would _
include the airborne radioactive concentration shown by the . building stack sampling system, supplemented as ~~
needed by the radiological monitoEl'g team. l 3.3.2 Criticality Accident This accident is postulated to occur during that portion i of the UF 6-UO2 process when as-received UF6 having substantial enrichment is introduced into water in a vessel calculated to be safe only if the UF6 is of modest enrichment.
Sensors in the FMO f acility will activate the criticality alarm. Personnel within the facility will immediately evacuate and proceed to the Staging Area.
A designated individual from the Fuels area will assume control for direction of the emergency until relieved by the Emergency Director.
i l
Criticality accident situations are categorized as site i Emergencies. Assessment of the on-site and.off-site impact will be made by the Emergency Director.
d WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Pag -
License No. SNM-1097 ,
Section No. 3 Ame nd . No '. O Amend. Date 1/18/82 Amend. Section(s)
~
6 Dose estimates at site boundary are set forth in Appendix G.
3.3.3 Uranium Hexafluoride (UFg) Release The postulated accident of a complete failure of a 30" diameter shipping container stored outside with the release of all the uranium hexafluoride (4800 lbs.) will result in the worst radiological impact on the environment of any WMD postulated accident. The occurrence will be immediately detected by plant personnel. The Emergency Director:will be immediately notified. If a fire is involved, the nearest fire alarm box will be activated. __ _
A designated individual in the affected area will direct the initial emergency activities until relieved by the Emergency Director.
Assessment of the magnitude of the off-site release will be made by the Emergency Director.
Dose estimates at the site boundary are set forth in Appendix G.
WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Pac ricense No. SNM-1097 Section No. 3 3-1; Amend . No . O Jaend. Date 1/18/82 Amend. Section(s) f
f . g NOVER Co lh h &
sMattrrs ottamtNT WILMINGTOM. NORTM CARouNa 284et-8591 PHONE (919) 34M4ll J.=en mo n. se.
January 19. 1983 J.R. Bradberry Jr.
Emergency Preparedness Coordinator Ceneral Electric Company -
F.C. Box 780 2 5 ',
Wilmington. NC 28402 M/C J-26 ._
Dear Brad In the event that you would request assistance for General Electric's Wilmington Plant f ro:a the New Hanover County Sheriff's Department, we would provida the followings f Investigative law enforcemens services. This would be to conduct any criminal investigation your plant requests.
All that has to be done is for a call to be initiated by your office to this Department and Officers will be immed-intely dispatched to conduct necessary investigation.
This Department will provide for your plant any necessary traffic control upon your request. This, of course, will cover any special activities or other traffic problems you have in and around your plant.
This Department will also provide Deputies upon your request, for protection of plane property in the event of disturbances or disorders. ,
n is Department has ninety-two sworn Deputies, all of **- *
' whom are cross-trained, so they can be used in various situations. Each Unifots Patrol shift has eight(8)
Deputies, along with several Detectives on each shift.
'we also have.tvo "Crise scene" officers who are available twenty-four(24) hours per day. , , ,
s b WMD EMERGENCY & CONTINGENCY PLAN Page Jense No. SNM-1097 Section No. 10 10-7 Amsnd. No. 1 Amend. Date 12/26/83 Amend. Section(s)
( . . . ,
I ' " * ~
ggMOVER cou SIttR1771 Dtf ARTMENT WILMINGTON, NORTll CAROUN4 284014398 fMONE (919) 34Msit Jesoge MsQuees Jr.
sherwr J.R. gradberry, Jr. (continued)
Additionally, this Department has radiological moattoring teams which, upon your request, could assist in' hey.-
hasardous spills or accidents. .
Therefore, in the event of an energency, this Department would be able to supply an adequate number of Deputies and Detectives with vehicles at any given time.
Within an hour's time. this Department can alert at.
least thirty (30) Regular and Special Deputies, if they are needed.
This Department is willing to participate in any preplanned activity %
on a periodic basis.
We stand ready to serve your plant as we have in previous years.
sincerely, j Joseph McQueen. Jr. [ .
JNcQ/ dss .
WMD EMERGENCY & CONTINGENCY PLAN Pag" License No. SNM-1097 Section No. 10 10-Amend. No. 1 Amend. Date 12/26/83 Amend. Section(s)
--g --
l North Carolina Department of
- r Crime 512 N. Schbury Street
& Pub:icSafe Contro: a?n P. O. Box 27687 Raleigh 276117687 (919) 733 2126 Jarnes B. Hunt, Jr., Govemor Heman R. Clark, Secretary March 17, 1983 Mr. J. H. Bradberry, Emergency Preparedness Coordinator General Electric Energy Products Division Wilmington Manufacturing Department M/C 3-26 Castle Hayne Road P. O. Box 780 Wilmington, NC 28401 -
Dear Mr. Bradberry:
This serves as the State of North Carolina's official letter of intent to respond to any emergency at your facility which has potential off-site effects.
Under North Carolina General Statutes the Department of Crime Control and Public Safety is responsible for the planning and coordination of any emergency g response that involves two or more State agencies. ,.
The direction of this response activity would be conducted through the State Emergency Response Team. Depending on the type and magnitude of the emergency, selected members of the Crime Control and Public Safety staff will assemble with representatives from other agencies at or near the emergency site. The senior personnel selected comprise a team of experts who have both authority and knowledge to efficiently and effectively allocate those resources of their agencies.
Please note that prior to the arrival of the SERT it is expected that exoerts at your facility would initiate any needed off-site monitoring, as well as make recommendations to local governments for needed orotective actions.
. ~ ~ . .
Initial notification should be sent both to the local government and to the State Warning Point. The receipt of this notification by the State will initiate notificaticn of the proper State agencies and will ensure their prompt response.
Ain [erely, el b
J -
.k k
Heman R. Clark ,
[- WMD EMERGENCY & CONTINGENCY PLAN . Page
- ense No. SNM-1097 'Section No. 10 10-9 Amend. No. 1 Amend. Date 12/26/83 Amend. Section(s)
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WMD EMERGENCY & CONTINGENCY PLAN Pa-License No. SNM-1097 Section KO. 10 10 .
Amend. No. 1 Amend. Da t? 17/?6/83 Amend. Section(s)
-_, , . , . ~ . . ,
i
.( .-
O_ok RidgeOperatons P.O. Box E
, OokRidge. Tennessee 37830 .
JAN 2 8 te!2 Mr. J. E. Bradberry
- Baergency Preparedness Coordinator maclear Ibergy Products Divisicn ,
General Electric Ca pany Poet Office Box 780 _
Wilmingtm, North Carolls 28401 ,. .
'Daar Mr. Bradberry:
BADIATICH IMDGEICY ASSIS':ANCE CEF:2R T!E::Irb SITE OuRC:5)
In respc.se to your letter of January 14, 1982, we are pleased to in-for:n you that the DCE RDC:S facility and teen are available to provide backup support ard assistance to the Wilmington Nuclear Ehergy Products Divisien cf the General Electric Cmpany in the event of a radiological -
accident or incident.
{ The RDC S facility is operated by the Cak Ridge Associated Universities (CMD) for the U.S. Department of Energy (:ET). Dr. Karl F. Hullr.or is the Director of RDC:5. The RDCIS facility and team are part of a centir.uing DCE program, however, the availability of REAC S assistance is dependent en cer.tinuing federal appecpriations.
The RDC:S provides m*.ern facilities for energency treatment for victim of radiation accidents. It is desigrad to coon with any type of radiation exposure accident which might occur in the Cak Ridge area. TN RDC:S staff is prepared to provide advice and assistance w!an radiation accidents occur cutside the Oak Ridge area. Since radiation accidents are infrequent, the PSCIS staff is involved on a daily basis in training prograrrs and radiatien expcaure st:adies utilizing the facility to assure its ccastant readiness. ,
RDCTS is also a source of infe: :aticn en the medical aspects of
- expcsure to radiation. A system cf recceds cf human radiatica effects fecm accidental ard medical expcsures has been established and serves as a basis for epidemiological studies as well as providirq useful data for these imcived in hardli..g radiatien cecidents.
I M*QUNI.
WMD EMERGENCY & CONTINGENCY PLAN Page
[
tense No. SNM-1097 Section No. 10 10-l' Amend. No. 1 Amend. Da te 12/26/83 Amend. Section(s)
I l
i
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I
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Mr. J. E. Bradberry JA.'! 2 8 ;32 no fee ce retainer is required to aneure the avellability of backup services by ItDC:5. However, should you desire to utilise the services of ItD C:5, we would expoet to recover thces costs which could reasonably?
be related to handilag such an incident 1 1'Wa=lall chargue billed to '
OtX cc GIAD by heepitals and physiciano. Teu are free to infers the mn1ame mogulatory Ccmaission that HDCI5 is avellable as a backup se port capability to par ongoing program. Information concerning the IERC:5 facilities, staff, services avellable and_ es for seeking *'
EIRC:5 assistance can be cetained by direct curt .'with the IERCIS Director, Dr. Karl F. Eutrier, Oak Ridge Associated Universities. .
Poet office Box 117, Oak Ridge, Tenw 37830 or. telephone (615) 576-3098.
We truet this information is adequate for your needs.
Sincerely, U*^ w Willian R. Bibb, Director s' .
f-En-13:RIE Reneerch Division - I!
ocs C.C.= h *,GIAU E. F. Rubner, GIAD C. W. B$ingtcri, ER-70, RQ, GIN d
J. W. Thiessen, IR-71, BQ, C:N
- w. P. Snyder, o:-10, cic J. W. mange, M-4,cuo
~
I
- 1 WMD EMERGENCY & CONTINGENCY PLAN Pa License No. SNM-1097 Section No. 10 10 ~l l
Amend. No. 1 Amend . Da te 12/26/83 Astend. Section(s) -l 1
1
l
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. l M M M C6pleUIIt3l(
+
xmmcxsomse Jesuary 16, 1984 t
Mr. J. R. Bradberry, Jr.
Energency Preparedness Coordinator General Electric Corporation ,
P. O. Box 780 -
Wilmington. North Carolina 28402
Dear Mr. Bradberry:
In the event that Easte 1 Distribution or ARPT would request assistance from the Greenville County Sheriff's Department for General Electric's warehouse at Donaldsoa _
Center, we would provide the following .,
Investigative law enforcement services. This would I be to conduct any criminal investigation your ware- '
house requests. All that has to be done is for a i
call to be initiated by your office to this depart- - i sent and officers will be dispatched ter conduct any necessary investigation. '
{ This departnesit will provide for your werehouse any
, necessary traf fic control upon your request. This, of course, will cover any special activities or other traffic problema you any have in and around your warehouse. .
This department will also provide deputies, upon your request. for protection of varehoose property in the event of disturbances or disorders.
This departamat has one hus. dred eighty-three (183) sworn deputies, all of whom are cross trained so they can be used ta various situations. Each L'niform Patrol shift has thirty (30) or more deputies, several I detectives on each shif t, as well as a Aiot Team. SWAT essa and Dive Team who are available twenty-four (24) '5 1
WCGEE SGEET / GCEENsuE SOUTH CMCUNA 29ect l803) 2715280 ,
l l
l WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Page
[ cense No. SNM-1097 Section No. 10-1 id. No. 1 Amend. Da te 12/26/83 Amend. Section(s) l
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Fase TW [ _
Mr. J. E. Bradberry, Jr.
- W *-
January 16. 1944 ,
hours per day. So therefore, in the event of an emergency. this departaset would be able to supply as adequate number of Deputies and lavestigators with vehicles at any gives time.
His departaset also has a Bomb Team well trained is handling explosive and incendiary devices. <.
i We stand rea'd y to serve'your plaat as we have during -
1
.the past..
j Y,aurs very truly.
( .
) ,
Joi neck stova
- l' Shor11f f .
. ,ne tag -
w- .
1 l
WMD RADIOLOGICAL CONTINGENCY & EMERGENCY PLAN Par i License No. SNM-1097 Section No. 1. 1 Amend. No. 1 Amend. Date 12/26/83 Amend. Section(s)
,- .. ,.- , , , , , - - -y y--w, y
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APPENDIX B ,
IMLLEMENTING EMERGENCY PROCEDURE LIST I
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Pagel WMD EMERGENCY E CONTINGENCY PLAN 10 '
l Acense No.-SNM-1097 Section No. APPENDIX B Amend. No. O Amend. Date 12/30/81 Amend. Section(s)
APPENDIX B EMERGENCY PLAN INDEX TO EMERGENCY PROCEDURES _
e CRITICALITY
- Criticality Coordination Sununary
- Plant Security
- Emergency Director
- Nuclear Safety Advisor
- Staging Area Supervisor -. .. ,,
- Plant Medical
- Recorder --
c--
- Facilities -
- Environmental Protection
- Licening & Compliance
- Survey Team
- Entry Team o FIRE OR EXPLOSION I
- Firt or Explosion Coordination Sumary
- Emergency Director
- Building Manager
- Industrial Safety Manager
- Fire Brigade
- Nuclear Safety Advisor
- Survey Team
- Building Search & Rescue
- Entry Team
- Facilities Manager ,
- Recorder
- Environmental Protection ,
- Plant Medical
- Licensing & Compliance
,_ Staging Area Supervisor Page-WMD EMERGENCY & CONTINGENCY PLAN
- 1 Section No. APPENDIX B _
License No. SNM-1097 Amend. Date 12/30/81 Amend. Section(s) _
Amend. No. O
a RADIOLOGICAL
- Radiological Coordination Sumary
- Emergency Director
- Fuel llanufacturing Building Manager
- Nuclear Safety Advisor
- Survey Team
- Entry Team
- Facilities
- Environmental Protection
- Licensing & Cogliance
- Stagihg Area Supervisor
- Building First Aid -
- Recorder
- Plant Medical g et e ENVIR0te! ENTAL - CHEMICAL HAZARDS
- Environmental - Chemical Hazard Coordination Sumary
- Emergency Director
- Building Manager
- Environmental Prot *:ction
- Facilities Manager
- Industrial Safety Manager
- Recorder-
- Plant Medical e BOMB THREAT
- Bonb Threat Coordination Sumary )
- Emergency Director j
- Building Manager Search & Rescue Team
- Emergency Situation Advisor
- Recorder
- Specialist - Plant Protection
- Facilities
- Security and Switchboard Operator Page WMD EMERGENCY & CONTINGENCY PLAN Section No. APPENDIX B 10 ~
icense No. SNM-1097 Amend. No. O Amend. Date 12/30/81 Amend. Section(s)
e SEVERE WEATHER
- Severe ideather Coordination Sunmary
- Plant Security
- Emergency Director
- Building Managers and Site Manager
- Nuclear Safety Advisor
- Recorder
- Materials Manager e CIVIL DISORDER, CONFRONTATION AND/OR INTRUSION.,
Civil Disorder, Confrontation and/or Intrusion doddination' Sunnary
- Emergency Director ..
- Recorder .
- Plant Security Director -
- Security
- Photographer o PRACTICE AND PROCEDURE ON EMERGENCY PLANNING h
- Responsibilities e
- Emergency Plan / Procedure Review
- Emergency Organization
- Training and Drills
- Equipment, Supplies, and Facilities i
i l
PagEl WMD EMERGENCY & CONTINGENCY PLAN 1" l' License No. SNM-1097 Section No. APPENDIX B Amend. No. O Amend. Date 12/30/81 Amend. Section(s) I
APPENDIX C EMERGENCY EQUIPMENT CATEGORIES
- =
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~1 Pagt WMD EMERGENCY & CONTINGENCY PLAN Section No. APPENDIX C 10 '
icense No. SNM-1097 Amend. No. O Amend. Date 12/30/81 Amend. Section(s) i d
5U n "e
- a. o
- " APPENDIX C EMERGENCY E@lPENT CATEGORIES I
o 3 : RESPONSIBILITY 5
5 GENERAL 5 5 Emergency Procedures and Instructions Emergency Preparedness Coordinator y
O O Emergency Preparedness Coordinator s
Miscellaneous Emergency Control Center Supplies
$ E o n Manager Plant Security / Facilities Manager
, [ Communication Equipment facilities Drawings Emergeticy Preparedness Coordinator b Q Emergency Preparedness Coordinator h Reference Material
~
E Manager Nuclear Safety Engineering /
gy e a Q PERSONNEL PROTECTIVE E@lPMENT Manager. Industrial Safety SE E Respiratory Protection -
8 E Protective Clothing m
n Y)
Personnel Dosimetry Devices l1
- o >
" Decontamination Supplies and Procedures
- z D.-. Manager Nuclear Safety Engineering
- RADIOLOGICAL CONTROL o
Portable Air Sampling Equipment Portable Survey Instruments
. .o (continued) '
t . .
E'. Appendix C
$2 EE RGENCY EQUIPMENT CATEGORIES RESPONSIBILITY E,
\ . $
- RADIOLOGICAL CONTROL (continued)
Manager, Nuclear Safety Engineering o E, Caution Signs and Labels
) Environmental Engineer j S g Environmental Sampling Equipnent
' " Manager, Nuclear Safety Engineering E o Wind Direction Sensor m
' E. E
, 0 I E O INJURY AND LOSS CONTROL k Emergency Medical and Surgical' Supply Kits Medical Director *
- e. Manager Industrial Safety Rf n Fire Fighting Equipment o 0 i
s 2 Manager, Facilities g DAMAGE CONTROL u, $ Tractors o et 'o Backhoe
" o u,
P { Trucks -
a g S. Shovels, Picks Wrenches, e'.c.
E Portable Welding Equipment Es
~ Portable Pumps Portable Electric Generators o
Sheet Metal, Pipe, Wiring, etc.
o E ,
i o
j 1
APPENDIX D EMERGENCY DIRECTOR DELEGATION LETTER ..
- 7, k
S I
i l
Page -
l WMD EMERGENCY & CONTINGENCY PLAN t^-
License No. SNM-1097 Section No. APPENDIX D l
Amend. No. O Amend. Date -12/30/81 Amend. Section(s) I i
i
GEN ER AL $ ELECTRIC December 16, 1980 coms. WMD Staff I
.a comm. Ext. 5656 aart.
G.E. Green J.A. Larson ocn. Wilmington Manufacturing Department J.H. Bradberry l l
aooness. M/C J20 ;
sunner. WMD Emerger.cy Director
, \
E. A. Lees, Manager Quality Assurance Effective December 22. 1980, and until further notice, __
i you are WMD's Emergency Director. The sequence of succession i
in case of absence and/or unavailability will be the same as --
currently indicated in e Emergency Manual.
701!%
c.
- K A. Long. General Mans. r f
jfimingtonManufacturingDepartment PJvH/JAL:2b
'l i
Page WMD EMERGENCY & CONTINGENCY PLAN Section No. APPENDIX D 10-2
. cense No. SNM-1097 '
Amend. No. O Amend. Date 12/30/81 Amend. Section(s)
APPENDIX E SUPPORT AGENCY EMERGENCY PLAN LIST ,
ac. ,,
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i I i
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' Pagei WMD EMERGENCY tr CONTINGENCY PLAN '
Section No. APPENDIX E 1^.
License No'. SNM-1097 Amend. No.. O Amend. Date 12/30/81 Amend. Section(s) ;
l
4 d
1 I APPENDIX E EMERGENCY PLAN 1
SUPPORT AGENCY CMERGENCY PLANS L
The following support agency emergency plans complement and provide backup support for the Wilmington Manufacturing ._.
Department Emergency Plan: ,
. ;. y .
a e North Carolina Disaster Relief and Assistance Plan y
a e North Carolina State Emergency Response Team -
- j Standing Operating Procedure 1
e Emergency Plan - New Hanover Memorial Hospital e New Hanover County Contingency Plan l
Hazardous Materials Transportation Accident 4
i i
1 i l
$ i Pagt WMD EMERGENCY & CONTINGENCY PLAN 10-:
Section No. APPENDIX E icense No. SNM-1097 Amend. No. O Amend. Date 12/30/81 Amend. Section(s) ._
7,__ .,_-_ , ._ , .. _ - , , . . . _ .
. _= . _ . _ . -- . . -
i APPENDIX F 4
SITE PLAN - WILMINGTON MANUFACTURING DEPARTMENT .
i 7
I Page-WMD EMERGENCY & CONTINGENCY PLAN 1 ^ -;
License No. SNM-1097 Section No. APPENDIX F Amend. No. O Amend. Date 12/30/81 Amend. Section(s)
Apetnotr F stTt MAP ar Tut wit.MinGTOM j\\d NW MANUFACTURIN(i DEPAT f? .
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- l l
4 l
i APPENDIX G DOSES FROM CRITICALITY & UFg GAS RELEASE ACCIDENTS .
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I Page WMD EMERGENCY & CONTINGENCY PLAN
- Section No. APPENDIX G _
License No. SNM-1097 Amend. No. 0 Amend. Date 12/30/81 Amend. Section(s) l
^- - - - --
' .= 2 k
4 DOSE / DISTANCE PLOT - CRITICALITY ACCIDENT 1
1 i
Intemrefation of Dose / Distance Plot I Plots showing the pmjected wholabody dose from'a criticality accident are shown in the accoganying figure. Some of the assugtions used in determining these plots are as follows: .
ts f9,34,,,, -,
i 1) The accident results in lo
/
- 2) The initial fission product inventory is zero.
.Only the volatile noble gases and fodines am considered to be released.
i
- 3) Dose estimates include a contribution from an
- individual's submersion in a semi-infinite cloud ,
i of ganen emitters and from the direct radiation '
from the accident (prompt neutrons and ganna rays).
A
- 4) Direction of the cloud is assumed to be toward the closest site boundary (122 m), southern direction.
' These dose / distance plots should not be interpreted to give actual j
estimates due to the conservative nature of many of the assumptions and calculations. Actual expected doses should be much less.
i l
l Page j WMD EMERGENCY & CONTINGENCY PLAN Section No. APPENDIX G 10 '
. cense No. SNM-1097 Amend. No. O Amend. Date 12/30/81 -Amend. Section(s) i _
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t i Amend. No. O Amend. Date 12/30/81 Amend. Section(s)
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DISTANCE IN METE RS WMD EMERGENCY & CONTINGENCY PLAN Page Section No. APPENDIX G License No. SNM-1097 Amend. No. O Amend. Date 12/30/81 Amend. Section(s)
N. a o a
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l Page WMD EMERGENCY & CONTINGENCY PLAN 16
- License No. SNM-1097 Section No. APPENDIX G Amend. No. O Amend. Date 12/30/81 Amend. Section(s) g I
DOSE TABLE - UFg RELEASE MAXIMUM INHALATION DOSE C0lWITMENT TO AN INDIVIDUAL AT THE NEAREST SITE BOUNDARY RESULTING FROM ACCIDENTAL RELEASE OF URANIUM HEXAFLUORIDE*
Dose Comitmant .
Organ (rem)
Lung 3.16 .
Bone 1.06 Kidney 0.176 -
Stomach 2.47 x 10-5 -
Il Small Intestine 3.16 Upper Large Intestine 1.24 xx 10-10 8 Lower Large Intestine 9.15 x 10-8 l
- Instantaneous release from a 30" cylinder l containing 4,800-lbs of uranium hexafluoride It should be recognized that there is an element of conservation in these accident calculations because of the nature of the materials involved. The postulated release would be in- the fann of HF and UO,3F 2
, both of which would be expected to be visible as a white cloud. Hydrogeh fluoride, in particular, is very irritating to the lungs and mucous membranes. hence, the natural reaction when exposed to this material is to hold one's breath and run from the cloud.
Thus, it is extremely unlikely that any individual would be exposed to the cloud for any length of time.
An exposure on the order of a few minutes would be most likely for an individual standing relatively close to the site boundary when the postulated incident occurred. Hence, the actual maximum dose comitments are likely to be a factor of 10 to 100 lower than those calculated.
WMD EMERGENCY & CONTINGENCY PLAN Page' Section No. APPENDIX G 10-:
icense No. SNM-1097 Amend. No. O Amend. Date 12/30/81 Amend. Section(s)
i 1
i APPENDIX H I
' PROTOGRAPH EXHIBITS
- 1. Emergency Control Center
- 2. Radio Communications Equipment within Security
- 3. Equipment Storage and Counting Area
- 4. Storage Cabinets and Counting Equipment ,
- 5. Counting Equipment 4
- 6. Storage Cabinets .
- 7. Counting Table .
- 8. Control Center Conference Area 1
- 9. Emergency Reference Manuals
- 10. Wind / Speed Output Console
- 11. Radiation Monitoring Output Console
- 12. Area Topographical Map
- 13. Folding Map / Chart Board
- 14. Communication Center
- 15. Communication Mode
- 16. Emergency Organiza*. ion Call Board
- 17. Portable Field Generators i
l l
1 I
i Pag:
WMD EMERGENCY f CONTINGENCY PLAN *~
Section No. APPENDIX G License No. SNM-1097 Amend. No. O Amend. Date 12/30/81 Amend. Section(s) _
j l
1
-. ,. .---,2t- . - - , .--,,,ey- y- y--- r- -- -+-y- - - - , --.- 4. y r - - --ev-,,--- --c-- - +
f APPENDIX I MAPS k
- 1. Castle Hayne Quadrangle North Carolina, 7.5 Minute Series
- 2. Map of Wilmington, North Carolina, Metro Area
- 3. Site map of the Wilmington Manufacturing-Department f
l
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1
/ WMD EMERGENCY & CONTINGENCY PLAN Page; icense No. SNM-1097 '
Section No. APPENDIX H 10-3 Amend. No. O Amen'd . . Dat 1/18/82 Amend. Section(s)
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APPENDIX J EMERGENCY PROCEDURES EXHIBITS FOR DEMONSTRATION PURPOSES ONLY 4
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l i WMD EMERGENCY & CONTINGENCY PLAN Pag 4 .ense No. SNM-1097 Section No. 10 10-31 Amend. No. 1 Amend. Date 12/26/83 Amend. Section(s). Append. J
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~'gacel Plant Bsergency - A situation affecting only a local area of v the plant and involving relatively few personnel. It may require evacuation of the 9
affected area, but it can be controlled by s
a.
the Building Manager and the resources normally at his disposal.
Operational Plant - A situation which presents a hasard to a I
Emergency or Site Emergency major portion of a plant operation, and/or to
' a significant number of personnel. The Baergency Director, site emergency teams and possibily off-site support agencies are required. For site energencies release of hasardous material to the environment may be involved to the estent that protective measures for off-site individuals may be r
warranted. ,
- 2. INITIATING SIGNAL: 14 cal Plant Emergency - Report of Situation and/or Fire Alarm Operational Plant Emergency or Site Emergency - Decision by Building Manager and Sounding of Second Alarm 6 .
- 3. EMERCENCY PERSONNET. WORK STATION: (Operational Plant' Baergency or Site amergency Only)
{
. Emergency Incident Function Control Center Location Stand-By Energency Director I
- Building Manager I Industrial Safety Manager I
- Baergency Response Team I Nuclear Safety Advisor
- rf X Monitor Teas
- 1 ~
Building First Aid 1 Building Search & Rescue K Facilities Manager X Entry Team - X Staging Area Supervisor * . I Plant Medical 1 Recorder X Environmental Engineer Z
[ 4. WMD PERSONNEL DESIGNATES:
- Function Prime Alternate Baergency Director Building Managers Wes
- JL Ha rmon Interia Ranung Site Manager FMO JE Bergman BP Bentley Foreman-Powder Prod FCO ter Poss EE Palmer '-
Foreman-TC&A**
- ESO WW McMahon JF Wolfe 1
AEG HE Spenner Foreman-Mfg (CR& Proc)
Foreman-AEG Bldg J RA Petelinkar N/A l
Facilities Manager RM McIver JW Summey N/A Industrial Safety Manager CF Shipp JC Bowell Baerg. Response Chief Nuclear Safety Advisor WC Peters SP Murray Rad. Prot. Supervisor Staging Area Supervisor RC Pace Foreman Fuel Support Site Plant Medical Leader CJ Schmidt RK B3111s Industrial Nurse Recorder GW McKenzie H Stern
- FMo only Ranking Site Manager
- Tubing, Cleaning & Annealing -
l License No. SPN 1097 Document No.~ 401 Rev. No. 5 Author JR Bradberry Date 11/37/83 Approval Signatures: Emergency Director b. I.
neergency Preparedness Coordinator Me, [/[vf
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- 5. ACTION SEqu(NCE (FIRE OR EXPtoSION) ' LEVER d (LOCAL *LANT EMERGENCY) OR (OPERATIONAL PLANT EMERGEb AND SITE DIERGENCV) ,
EMERGENCY RUILDING INDUSTRIAL EMERGENCY NUCLEAR SAFETY m10t m EWIR0lpl[RTAL Rutt0 lng SITE y 3I g DIRECTOR MANAGER SAFETY MANAGER RESPONSE TEAM ADVISOR SPECIALIST SEAtol & RESCUE RE-ENIRT TEJRt ., ,
LOCAL Pt ANT EME GENCY . ,:
St:ndby Report to Scene Report to scene Report to Scene Report to Scene Repor o one Standby Report to Scene l5tandby l of Incident of Incident of incident of fuel o se of Incident i Account for Manufacturing knufacturing Personnel . Ftres Fires
- Detemine .
Severity Evaluate Severity Call for Nuclear Safety Support Search for Personnel
, k:
. Decide Need If Needed Assess Radiattori Assist As leeeded If Required .
l for first Aid Safety Potential , .
- e?
Of rec t Fire l Fight fire l '
4:
Fighting Direct Survey Survey Decide need Operations Team If Factittles .} l3
- for Evacuation Necessary (g g Sound Second Request Medical Request Medical Advise Fire -
i Alam If support or Out- Support or Out- Igghting Teae J. '. '
Warranted stee Fire side Fire f g, fighting Equip. Fighting Equip. '
As Needed As needed -
t, i DPERATIONAL PLAI T EMERCENCY AND 5 TE EMERGENCY Report E3 h inta1a Report te Report to
- Report to Repert to Reperg gg Emergency Communications Emergency Emergency Emerpacy Wit ncy Emerpacy metrel Centsr Control Center Control Center Centros Center Centrol Center Easte, Confim Maintain On- Advise Advise Emergency Support site Control Emergency Director of ,l Of Fire Olrector Radiation Evaluate ,
$ltuation of situation Situation Environmental i e
- we ity mn Ass 1st As Needed Estended .
Evacuatloa , , , ,; . t i
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equest Medical :1 -
lAssistAsIleeded Direct Support if Required Additional g i Personnel . q .,l, e Report Status . *L., .. ,
scide heed for of Situation * }f Retside Fire - & J Call For 1-fighting 8
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' b.9 IREMENTS: (FIREAND/0REXPLOSION) 9 }[{
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! CY l WD Department General Manager At the discretion of the .ilding l Manager ,
NRC Region II Within 30 days Radiation Protection Branch of Within 30 days -
the N.C. Department of Human Resources OPERATIONAL PLANT EMERGENCY OR SITE EMERGENCY WD Department General Manager Imediate Notification ,,
Nuclear Energy Products At the discretion of the Emergency i
Division General Manager Director (Operational Plant Emergency);
Imediate Notification (Site Emergency)
Manager - NEP&QA0 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Operational Plant i r Emergency); Imediate Notification (SiteEmergency)
Manager - Safety & Licensing At the discretion of the Emergency Operation (NEProjectsDiv.) - Director '
Manager - Taxes & Insurance Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> I (NuclearEnergyFinanceOpn.) -
NRC Region II Imediate Notification Radiatio'n Protection Branch of Imediate Notification - ~ '
- the N.C. Department.of Human -
Resources N.C. Division of Environmental Imediate Notification if significant =-
Management (Wilmingtonoffice) smoke release off-site or if involving-hazardous chemicals Environmental Protection Agency Within 24. hours - Site Emergency Only New Hanover County Sheriff Dept. Imediate Notification of a Site Emergency and if off-site hazard potential f New Hanover County Civil Imediate notification if a Site Preparedness Coordinator ' Emergency and if off-site hazard potential .
, _ . - - - - - - , - - . , , , < - . , , - - - . , - . - , - - ,n- -.----..--,,,.,-.-.n , , - - - ~ . , , , - - , - - , , - , _ - - - , , - , -----,w---,.--
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. -y IREMENTS: (FIREAND/OREXPLOSION) 1;{ 6. Com m CRITERIA New rial Hospital Imediate alert if injur.ies/ contamination Ogden Rescue Squad Imediate Notification if medical l transportation assistance is required (FirstChoice)
New Hanover County Rescue Squad Imediate Notification if medical transportation assistance is required (Second Choice)
Wrightsboro Volunteer Fire Imediate Notification if fire Department fighting assistance is required ~~
(FirstChoice)
Castle Hayne Volunteer Fire Imediate Notificatio'n'if fire Department fighting assistance is required (Second Choice)
Wilmington Fire Department Imediate Notification if fire fighting assistance is required
( N.C. Department of Labor
-(ThirdChoice)
Notify within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if a fatality .,
s occurs, or if 5 employees hospitalized Factory Mutual Engineering - Notify within one week American Nuclear Insurance ,
Upon recomendation of Manager, Taxes and Insurance N. C. Department of Immediate if Hazardous Materials Human Resources are released or spilled to the environment. . .
O s
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, I'.g 2 EMEMij N E-[2 $ M b
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'. , EMERGENCY PROCEDURE
- v .
SITUATION: EXPLOSION LEVEL: Local Plant Emergency or Operational Plant Emergency and Site Emergency INITIATING SIGNAL: 1-1-1-1 on Fire Alarm OBJECTIVE The Emergency Director will respond only after the decision of the appropriate manager to escalate a condition to an Operational Plant Emergency or a Site Emergency. The Emergency Director then has full responsibility and authority for the implementation and administration of cmergency actions. He is responsible for the overall control and direction ~~
of the emergency organization and control of affected areas. Primary objective is to monitor all activities in such a manner to assure the safety and well-being of plant personnel, the public, and the environment.
IMPLEMENTING ACTIONS / COMMENTS o Alarm Sounded o Fire alarm system
/' o Alarm enunciates 4 times o Communicate with o Wait some time, then call l Security Security for _information as 1 necessary Gate 1 5494 ECC 6181 o Report to ECC on o Alarm is 1-1-1-1 alarm o Recorder will report on alarm o Verify support o Support: Nuclear Safety Advisor members'are at ECC Facilities Mgr.
Recorder ~
Env. Engineer Re-entry Team o Establish Status Report '
communication with o Area involved; building, Building Manager containment, environmental '
(continued)
License No. SNM-1097 Document No. 401-A-1 Rev. No. 2 f
athor JH Bradberry Date 4/1/82 Approval Signatures: Emergency Director // ws Emergency Preparedness Coordinator lui. Mdd h
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RE~OR-EXP EMERGENCY DIRECTOR IMPLEMENTING .f*
/ COMMENTS
'involv'ement , offsite consequences o Hazard involved; radioactive materials, fumes, pyrophoric metals, criticality risk, gas or potential explosive fumes, chemicals, i.e. fluorides, ammonia, hydrogen, acid, akalyd, solvents, PBC. ,
o Personnel risk; potential hazard to people in area, building,
- people missing, injurie.s..
o Admonish to remove unnecessary personnel from scene.
o Call General Manager (5666) and inform of situation.
o Brief Emergency Staff. ,
=
o Communications o Radio available at ECC -
o Phones in ECC- 6183/6184 (local) o PA system available to FMO through criticality system o PA system ESO 411, FCO 422 o Fire fighting teams o Status - Leader Personnel on duty m .
- Emergency vehicle More required o Special equipment o Mask 1 Fire extinguisher l Suits . ,
Scott Air Pak. ,. l o Method - o Firefighting , .
' Water CO2 Other
(, o Risk involved Criticality "
Explosion i
o criticality hazard o Use the following guidelines for )
~ fire fighting methods:
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EMERGENCY'DE M C $
'./ COMMENTS
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Controls j '
er 1. Water MAY NOT be used.
i B1 r Warehouse i Dry Powder Warehouse 2. Use CO2 (first choice) 4 ' or foam (second choice).
2' PTL Blender Area Old Stacker ,
l . Bundle Forest 1. Foam MAY NOT be used.
I Pellet Cabinets Rod Storage Cabinets 2. Use CO2 (first choice) i or foam (second choice).
o Call Medical - have standby o Medical readiness o verify personnel on duty I
o Emergency vehicle driver available pr .o Who.will support '
! First Alder '
External o Evacuate unnecessary o Move personnel from accident
- personnel scene o Account for personnel i l o Determine requirement for search l l
and rescue o Dispatch radio, megaphone and' 'r
- writing materials to FCO/REO staging area if required o Establish weather o Have recorded wind direction, conditions wind speed, stability class i (call CP&L for this) weather -
condition . ..
4
- o Have airport called for weather * .
. verification backup o External support o Fire - Have Wrightsboro required Volunteer Fire Dept. called f
o Have Security escort emergency vehicle to scene
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IRg IX EMERGENCY DIRECTOR _)
IMPLEMENTING .
/ COMMENTS
? l o Assess sit o Consider having done - issue i instructions Radiation hazard Air samples Criticality hazard Secure dam Explosive hazard Secure power lines, gas lines, ' .
and/or other critical utilities ,
Electrical hazard Secure chemical lines Chemical hazard .
Injuries hazard Other potential injury sources -
o Request Nuc. Safety o Radiation measurements Manager to handle radiological measurements for radiation potentials
- and. report results o Request Facilities o Damage Control * '
Manager to provide Cut off power assistance. Shut off dam
- Block ditches Isolate tanks, chemicals, gas, etc.
o Record actions taken and time i
o Search and rescue o Look for missing persons as -
required .- ..
o Damage assessment o If potential radiation hazard, involve Re-entry Team and Nuclear Safety Advisor . 1
~
, o Notification of o Potential for' injuries Medical (5333) ,
. I o Identify location j o Radiation / contamination presence o Rescue Squad o Have called if Medical Director ,
assesses need o Notify Security .
o security to provide escort to site of emergency l
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EMERGENCY DI '?stfi..
. .P j' / COMMENTS
- . ; ;4-f o Notify G4 r o' Provide status report Manager (5 Damage
! Injuries .,
Impact on production
! o Notify Local, State & o Designate Licensing & Compliance !
! Federal agencies representative to notify
- o List in Coordination Summary
. Per Nuclear Safety Advisor
- recommendation Per Environmental Protection Engineer recommendation - ,
Per Industrial Safety i recommendation
! o Notify EECR o Preparation of news release
! Communications and/or GE Corporate management
] Director I /" Total control o Terminate emergency established ,
o Reestablish ECC to pre-incident ,
! readiness. -
o General Manager o Notify incident under control Significant points
- i o Critique incident o Critique the accident ASAP after
! accident, include:
- 1) Employees involved
- 2) Spectators as appropriate ~' r -
! - 3) Industrial Safety Mgr.
l 4) Building Manager
- 5) Nuclear Safety Advisor -.
i
' 6) Recorder -
- 7) Facilities Manager
- 8) Others as deemed necessary -
o Should tape discussion "
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! o Have incident report written i
i o Initiate investigation into ,
j cause as required.
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J COORDINATION
SUMMARY
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SITUATION: TT t
- 1. CIASSIFT LEVEL:
Site Energency -
A situation which presents a hasard to
, a major portion of a plant operation, and/or to a significant nuncer of personnel.
The Emergency Director, site emergency teams and possibly off-site support agencies are
(
l re'Iuired. Release of hazardous material to l the environment may be involved to the extent
- that protective measures for off-site individuals may be warranted.
I i 2. aITIATING SIGNAL: Criticality Alara 3 .- EMERGENCY PERSONNEL WORK STATION: '
Emergency Staging Site Function Control Center Area Gates Stand-By
~~
Beergency Director X . . ,
Fuel Manufacturing Bldg Manager X Nuclear Safety Advisor X -
Staging Area Supervisor X
- Entry Team X Monitor Team X
, Plant Medical I
, Plant Security X -
Recorder X
- i Deergency Situation Advisors X WMD Advisory Staff X
( Licensing & Compliance Environmental Engineer X
X E&CR Manager 1 -
- 4. WMD PERSONNEL DESIGNATES:
~
Function Prime Alternate Interia i
! Emergency Director EA Lees JL Rarmon Foreman-Powder Prod.
Fuel Manufacturing Bldg Mgr JE Bergman SF Bentley Foreman-Powder Prod.
Nuclear Safety Advisor WC Peters SP Murray Red Prot Supervisor Staging Area supervisor RC Pace Foreman Fuel Support N/A Plant Medical Director CJ Schmidt RK Hollis Industrial Nurse Plant Security Director JE Bradberry WJ Hendry Burns Supervisor i Recorder GW McKenzie
- B Stern Foreman-ChMe Licensing & Compliance CM Vaughan MD Foleek , N/A E:nergency Situation Advisors WW McMahon JF Wolfe . Fotenan-Mfg (CR&JP) -
1 1
CF Shipp N/A l DA Burns JM Miss N/A TM McLamb GF Bartelt N/A WJ Hendry CM Vaughan N/A -
Environmental Engineer WB Smalley T Crawford N/A
- Tubing, Cleaning, & Anneal -
. . . - - - . . . . . . . . . . . . . . . . . . . . . . . . - - . . . . . . . . . . - - - - ~ . . - . . . - - - . . -
! License No. SNM-1097 Document No. 402 ,
pav. No. 5-Author JR Bradberry Date 11/23/83 s .
Approval Signatures Emergency Director [A w - -
Emergency Preparedness Coordinator k -
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- 5. Atilon StoutmCf (CRITICAttif) tilft ; (5ITE EMERGthCT) futt MAnufAliuolic 11U01f Aa SAf fly STAGi n AptA PLAtJT 5(Cually (MtRGtsC DWCW RC-ENTRT TW mmst N Stif PLAlli IEDICAL RECORNR sulLDING MAnAGin ADVISOR SurtRVI504 I#til % ACil0N - N0kIAL_Dal 5HIFT OPERAft0hL .
Report to Emergency Report te Emeroency Report to terrgency Report to 5taging Aeport to Emergency Report to Emergency l Stamey l Report to Esergency Control Center Control Center Control Center Area Contral Center Control Center Centrol Center ImITIAL ACTION - mitii 9tlF15 M [ g m01 i ~*
Call After-Hour Report to fuergency Report to fuergency Report to faargency Report to Staging Report to faergency Report to faergency l Staaey l' Aspart to Emergency Emeraency nottfl. Control Center Centrol Center Control Center Area Control Center Control Center Centrol Center citton List IMPtfGIIING ACilf% .
lClose51t2 Gates l lConfirmSupport lAssistAsneededl Otrect the Re-Entry
& survey Teens Assure Staging Aree Security Survey Factitty & Report to 5taging secument Assess Materd Aree & survey Occurrences Monitor Activities Account for All Personnel
& Direct Operations Personnel Report Results to Report Sesults te nuclear Safety Ihsclear Safety
, Adviser Adviser laterpret Re-fatry ,
& k rvey Te a Reports Evaluate Further Actions (1 or 2 Belen)
- 1. NON-CRITIrat SIT l Ail 0N
' ,l 0 pen sitj Cates l Initiate Return 511 erie Alarm to Operations Sourd All Close ' ,
Aelease Personnel -
le Protective '
Clothlag 4 Survey facility for Centeotnettaa lavestigate Cause telease Anmelatag Garr6cade if of Alarm Persammel Necessary -
' 2. CalifCAL $1TUAilhel Secure Area & sequest Medical Reconfire Personnel OI> tele Date n,ce.ggru Personnel Report to Emergency Centrol Access Support Accountability l As M rected l i Surters Centrol Center l
8 Initiate Esternal Evaluate Affected a hapert te IInclear esport to anclear
[ hec Communications Areas & Personnel Safety Adotter Safety Adotter
, Decide IAtether/How Aggggg gyggggg As hecessary
- Eriticality is Stopped Persennel Ireesfer lajured ,
lattlate Correcttee - t Assist to lenspital Actlen Plas
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- 6. COMINICATION REQUIREMENTS: (CRITICALITY) i r
_; FUNCTION CRITERIA -
f nee Department General Manager Imediate Notification
! ' Nuclear Energy Products Imediate Notification Division General Manager ,
Manager - NEP&QA0 Immediate Notification .
,h. r
- i. ' Manager - Safety & Licensing- At discretion of Emergency Director
- . Operation (NE Projects Div.) ,
P I Manager - Taxes & Insurance Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Nuclear Energy Finance Opn.)
American Nuclear Insurers Upon recommendation of Manager Taxes - - -
r and Insurance or Regulatory Compliance
-~
Manager -
i
. NRC Region II Innediate Notification
) NRC Director of Management Imediate Notification i i g Infonnation and Program Control I -
Radiation Protection Branch of Imediate Notification the N.C. Department of Human Resources _
tl l
New Hanover County Sheriff Dept. Imediate Notification if off-site hazard potential l New Hanover County Civil Imediate Notification if off-site l
- Preparedness Coordinator hazard potential l New Hanover Memorial Hospital Imediate alert if injuries / ,
contamination or overexposures to -
i radiation exist ,
i 1
Ogden Rescue Squad Imediate Notification if medical .
! transportation assistance is required
! (FirstChoice)
(
! New Hanover County Rescue Squad Imediate Notification if medical ..
transportation assistance is required
. (SecondChoice) l; l Radiation Management Corporation Imediate Notification if radiation
' medical consultation assistance is
/ required ,
i N.C. Department of Labor Within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if a fatality occurs, or 5 employees hospitalized i -
1 EMERGENCY DIRECTOR i
gP EMERGENCY PROCEDURE
,ITUATION: CRISECALITY LEVEL: Site Emergency ,
INITIATING SIGNAL: Criticality Alarm or Phone Call During Off Hours OBJECTIVE The Emergency Director has full responsiallity and authority for the
- icplementation and administration of emeegency actions. He is responsible fcr the overall control and direction of the emergency organization, and the control of affected ares. Primary objective is to monitor all activities in cuch a manner to assure the safety and well-being of plant personnel, public, and the environment. He is responsible to determine if site support 10 sufficient to handle the conditions and request support as required. ..
IMPLEMENTING ACTIONS / COMMENTS o Alarm o Criticality signal sounds in FMO l
o Alternate signal through fire alarm in all buildings 1-1-1-1 f
Proceed to Emergency o Check high range gamma Control Center instrumentation in ECC o Ascertain if criticlaity is cycling o Have rad level checked at staging area 1
O Activate ECC o check radio operation status Communications (verify channel) ~~ ,
o Confirm gates (exists) closed i o Place someone at radio and on -
phone to receive and record information -
License No. SNM-1097 Doc,ument No. 402-A-1 Rev. No. 3 Author JH Bradberry' Date 12/26/83-f
) proval Signatures Emergency Director i$< 4h -da[> - -
Emergency Preparedness ,j g Coordinator -
,_;- J , W jr er
CRITICALITY EMERGENCY DIRECTOR MPLEMENTING ACTIONS / COMMENTS _
o Verify supo begs o Support - Fuel Bldg. Mgr.
are at ECC ing. Nuclear Safety Advisor Have Securit 11, -
Recorder if necessary Reentry Team monitor Team E&CR Manager Security Supervisor o Interim o If rad levels detected, have Security notify Emergency Organization Prime & Alternate members. ,
o If alarm determined to be false skip to "non critical ~"
situation". Have activities performed.
o Notify Emergency Director o Staging area rad o Check rad levels at large levels warehouse; if acceptable
> 250 mr/hr assemble there if not o Reassemble at parking lot in
([ front of PCO ,,
o Recheck rad levels - record readings o Make PA announcement for people to walk not run, provide reassurance o Instruct people to keep badges o Direct Nuclear Safety Advisor'to set up quick check teams for activation monitoring ,
o Request Staging Area Manager to control people for quick check ,
o Have air samples taken upwind / .
downwind for potential release ,
o Inclement weather - o Have personnel moved to large radiation readings material warehouse (take bolt cutter). or FCO - control area
(% people to.be kept segregated and together .
9
CRITICALITY EMERGENCY DIRECTOR *
/ MPLEMENTING ACTIONS / COMMENTS r o All others have stand in aisle 1
- - way together 4
O People accouh bility o Have all units report in ,
o Contractors - Daniels Canteen Cleaning o vendors o visitors O Alada valid and rad o Direct Nuclear Safety Advisor to i level < 250 mr/hr at set up quick check teams for staging area activation
~~
o Assign Staging Area Manager to
! control people for quick check .
o Take air samples upwind /
downwind for potential release o People accountability o Have all units report in
- " o Contractors - Daniels I Canteen j Cleaning
~
o Vendors .
1 o Visitors o Medical o Activate Medical Team at Staging Area, if needed j
o Authorize actions to silence . ~. ' ' -
alarm o Inclement weather - o Have people moved to shipping ,_
no radiation readings area of building o Post people at doors to prevent ,
reentry into FMO/FMOX until all clear given -
o Move and maintain people in control area clothing close to south side of building, keep together f
Source location o Activate Monitor Teams to
, measure rad levels - determine source location
CRITICALITY EMERGENCY DIRECTOR MPLEMENTING ACTIONS / COMMENTS m e o Map radiation levels for f building area o Monitor exposure of Sea'rch &
Rescue and Survey Teams o Establish weather o Wind direction, speed, barometer conditions reading, dry, wet, cloudy, clear, etc. Have these recorded.
1 o Known false alarm o verify radiation readings.
o Allow Security to open gate 1 and lobby _
j ocanterminateaccountabikityand,_
i staging area monitoring o Skip to non-critical situation o Notify General Manager
([iMissingpersons o Staging Area Mgr. should conduct search for personnel in other '
buildings or at their homes o Search & Rescue o Activate search & rescue for missing persons upon concurrence with Nuclear Safety Advisor o Exposure records must be maintained o Review emergency exposure limits ~, ,
Wholebody , _ ,
25 rem protective .
75 rem lifesaving Extremities '
100 rem protective -
300 rem lifesaving , , ,
o Assure wearing of dosimeters c Injury status o Inquire from Staging Area Mgr.
of injury status
{
e
, , , _ - - - - - , e
CRITICALITY EMERGENCY DIRECTOR'
/ COMMENTS g7MPLEMENTING ACTIONS I
Evaluate da o Monitor Team reports radiation / contamination / release
. )
o criticality warning system -l status o' Reentry Team reports
- o staging Area status o Injury reports o call offsite support o Concurrence with Medical. '
~
Director l o Ogden Rescue Squad and/or NH _.
Resque Squad - transport"- .
accident victims to hospital .,_
o NHMH needs notification that personnel being transported and contamination / radiation status 4
o Rad Safety personnel to i I accompany patient to hospital I and support hospital personnel o Notify Security ,
! o Security to escort emergency i vehicle to accident scene o Offsite evacuation
! required o Notify Civil Preparedness (Raleigh) and/or State warning pt. Highway Patrol o Notify Sheriff's Department o External . ~, * '
contamination o Identify personnel with external contamination and initiate appropriate decontamination ..
procedures - i.e., showers o Interviews o Have activated persons initially ~
interviewed , ,
, )
o Ascertain location , , l o Orientation o Flash observation f .
o Utilization of tape recorder would be beneficial l
- - - - . - - .,- .-s_ - . ---. -, - --
, - , , - , _ .- - - - . - - - . - - - - - - _ . . ~ - , , , -
l CRITICALITY EMERGENCY DIRECTOR' FMPLENENTING ACTIONS / COMMENTS g o Activated itensk o Collect pens, pencils, rings, l '
T' belt buckles, hair clips,
. jewelry, watches, dental 4
applicances, etc.
- o Record location on body t
o could be exposure problem, place t in container or some distance l away o Medical aspects if o Collect samples required fo'r -
) person activated exposure analysis ' ' -- -
~
j l
Blood samples i Hair ,
~~ '
! Mail clippings ; -- -
2 '~
o Monitoring devices o collect needed exposure history of personnel o control criticality o coordinate development of plan i to control and secure criticality o Review current status l[3 Status Missing persons
- . Injury status.
! Exposure levels building I people i l Accident locations Control status 1
l o Update General o Report on current condition and j Manager hazards still remaining I o Notify local, state, o List in Emergency Procedure , * ** '
j & federal agencies ..Per Nuclear Safety Advisor i Licensing Consultant i Industrial Safety .
j License & Compliance Audits .
l Person to do i o Notify E&CR o Prepare news release ' ' ,
- l Communications -
Specialist . o Notify GE Corporate % l o Notify insurance company li
\
i
(.
i t
CRITICALITY EMERGENCY DIRECTOR' f*MPLEMENTING ACTIONS
/ COMMENTS l Emergency coeW olled o Terminate emergency o Send personnel home o close paint o secure operations o cut off utilities (as required) o Release people from site o Security o Egress controlled
. 1 o Unlimited access
~~
O Critique incident / o Critique accident ASAP o Assimilate all o Government interest information Release Exposure i Injuries
- Deaths Destruction ,
Downtime expereinced/
anticipated o Pictures, descriptions, observations pertinent o Collect all charts, records, tapes, pictures, etc. for reconstruction of incident o Recollect all o Restore ECC to state of
- e ,
. readiness instruments, reinventory cabinets, , .;
restore to pre- 1 incident readiness .
lichi CRITCAL SITUATION .
i o Contamination status o Have Reentry Team perform -
surveys of building corridors, ,
exits, passageways ,,
o Have Security Supervisor
/
instruct Guards to open gate 1 and lobby. .tk) emergency exists. .
t 1
l CRITICALITY . EMERGENCY DIRECTOR
- MPLEMENTING ACTIONS / COMMENTS 3 O Personnel release o If no contamination present o Direst Staging Area Manager to release personnel in protective clothing first o Release personnel in street clothing o Have Guard open ECC gate
, o Rave Staging Area Manager report to ECC for critique .. ,
o critique incident o Critique incident. prior to termination ~~
should include: e- - -
Staging Area Mtnager I, .
Building Manager Nuclear Safety Advisor ~
Recorder Communications Security Force Representative Survey Team Representative m
([ Reentry Team Representative
~
o Should be used to determine problems and recommend solutions o Terminate emergency o Restore normal plant operations status }
o Notify General Manager o Written account o Incident to be documented should include problems noted, recommendations, action J tems .s --
who is responsible o ReectabliAh ECC to o Assure instruments communication -
pre-incident devices, equipment. returned readiness o Have inventory performed, .
. cabinets restocked ,
( o Non-essential equipment turned , ,
i 4 off -
C.
CRITICALITY' DESCRIPTION FOR 10" FISSION ENERGY RELE MISSING PERSONS PROJECTED IOTAL ABSORBED DOSE (PROMPT NEUTRON + GAMMA)
-. DISTANCE FROM Acc! DENT 10m 30m 100m 200m 3m
- (10 ft.) (30 ft.) (100 ft.)- (300 ft.) (600 ft.)
l N
z 44R 4R 1R
'5mw 1 min. 4400R 440R
.r 508 50 4.6 - 1.1
,,$ 10 min. 5078 mm 53 4.8 1.2
_ $g 30 min. 5306 531 ou 4.9 1.2 I hr. 5428 543 54
[xo ,
553 55 5.0 1.2
!a. 2 hrs. 5530 RE-ENTRY TIME / DISTANCE DOSE RATES DISTANCE FROM ACCIDENT 10m 30m 100m 200m 3m (10 ft.) (30 ft.) (100 ft.) (300 ft.) (600 ft.)
U z
1 min. 22000 R/hr. 2200 R/hr. 220 R/hr. 20 R/hr. 5 R/hr.
10 min. 2200 R/hr. 220 R/hr. 22 R/hr. 2 R/hr. 0.5 R/hr.
700 R/hr. 70 R/hr. 7 R/hr. 0.7 R/hr. 0.2 R/hr.4
, 30 min.
m 0.06 R/hr 1 hr. 300 R/hr. 30 R/hr. 3 R/hr. 0.3 R/hr.
100 R/hr. 10 R/hr. 1 R/hr. 0.1 R/hr. 0.02 R/hr g 2 hrs.
5 R/hr. .5 R/hr. 0.05 R/hr. 0.01 R/hr 5 hrs. 50 R/hr.
TABLE 6.1 ,
EMERGENCY EXPOSURE CRITERIA Protective or . Life Saving Corrective Actions Actions 25 rem 100 rem
- 1. Planned. dose to the whole body shall not exceed 100 rea 300 rem
- 2. Dose to hands and forearms (including whole body component) should not exceed
- 3. Rescue personnel should be volunteers or professional rescue personnel (e.g. firemen who " volunteer" by choice of employment).
- 4. Persons perfoming activities should be broadly familiar with the consequences of exposure and having documented exposure history.
- 5. Other things being equal, volunteers above the age of 45 should be selected, when possible.
- 6. Internal exposure should be minimized by respiratory protection and contamination controlled by the use of protective clothing. .
l l
1
- 7. Normally, exposure under these conditions shall be limited to once in al lifetime. >
i I
These criteria are in accordance with applicable recommendations by the National Council on Radiation Protection and Measurements (NCRP #39) .
e
- . g
NUCLEAR SAFETY ASSOCIATES QUICKSORT METHOD OF ESTIMATING PERSONAL EXPOSURE TO DIRECT RADIATION ERCH A NUCLEAR CRITICALITY In the event of a nuclear criticality, the first step toward estimating the dose to exposed persons is to identify the exposed individuals by a
" quick sort" procedure. Radioactivity induced in an indium foil worn on a person by fission neutrons will likely permit measurement of the activity by an ionization chamber, GM, or scintillation survey instrument. The -
relationship between indium foil radioact1vity and total neutron plus gamma-ray dose depends strongly upon the neutron spectrum, the gamma ray ~~
to neutron ratio, and the orientation of the indium on the person exposed to the critical event. Consequently, any estimate of personal dose made by this method is quite uncertain. Without definitive information about these factors, it is advisable to consider a person significantly exposed if he is wearing an indium foil badge with any detectable induced radioactivity.
Bases The bases on which the following procedure and graph have been derived are:
- 1. The exposed person is wearing an indium foil 0.002 inch x 0.5 inch x 0.5 inch weighing 0.06 gram.
- 2. The person is exposed to fission neutrons.
- 3. The gamma to neutron (kerma) ratio is'2.8.
4.- The quality factor of neutrons is 2.
- 5. The indium foil is read by a Cutie Pie, ionization chamber survey ._
instrument with the beta shield closed and the chamber in contact with the foil. (The center of the ionization chamber is about .
4.5 cm from the foil.) -
p f*
f
Page 2 NUCLEAR SAFETY ASSOCIATES i
g(.: -
Procedure This procedure should be executed in an area of normal or near normal background radiation level and to badges that are not otherwise contaminated with radioactive material.
- 1. Obtain a portable radiation survey instrument of'the ionization
, chamber type. ,, ., [ -
- 2. Check the operability of the survey instrument.
- 3. Close the beta shield on the survey instrument.
- 4. Read and record the background radiation fa~vd1 at the place where ,
badges are to be surveyed.
- 5. Remove the indium badge from the wearer. Record the~earer w
, and the badge number. .
- 6. It is advisable to wipe the badge with tissue to remove any loose, surface contamination before surveying it with an instrument. -
i 7. Place the indium foil in contact with the face of the ionization ,, ,
chamber and read the exposure rate (mR/hr). l
~
, 8 ;' Record the survey instrument reading 6f the indium foil, the time, and the approximate time elapsed since the nuclear criticality along with the badge number and wearer's name.
- 9. If the indium foil reading is higher than b'ackgrouitd, assume ,
that the wearer of the badge may have experienced a significant direct radiation dosa.
~10. Estimate the direct radiation dose to the wearer of any badge reading higher than background. '--
- a. Locate the curve which corresponds to the tiene elapsed between the criticality and the measurement of badge indium activity.
~
- b. Using that curve read the value of the'$adiation dose from the ~-
. '~ ordinate of,the graph which corresponds to the measured -
l radioactivity of the foil, on the abscissa of the graph.
i L. .
l l -
1 DIRECT DOSE ~ TO A PERSON IRCM A NUCLEAR . CRITICALITY ,
AS ESTIMATED BE INDUCED RADICACTIVITY iN INDIUM FOIL
- f 0.06 gram Indium foil I
ium foil radioactivity measured with ionization
. c . -
. survey instrument (Cutie Pie) with beta shield closed j -w - .
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9 NUCLEAR SAFETY ASSOCIATES T
ISOGRAMS OF ATMOSPHERIC DISPERSION FACTORS
, (Atmospheric dispersion factors relate the atmospheric concentration downwind to a unit release rate of the substance into the atmosphere.
Thus the product of,a release rate, and an atmospheric di.spersion factor between the points of release' and reception gives an estimate of the concentration of the point of reception. Likewise, the product of a time
. integral of release rate and an atmospheric disparsion, factor PIE ducep ,
an estimate of the time integrated concentration, or exposure, at.the ,
~
point of reception. .
- ~ry . _
Bases
~
! Atmospheric dispersion is largely influenced by weather conditions and wind speed. Mixing on the les side of a building from which radioactive I
gas is discharged may also increase the dispersion within a few hundred Factors of atmospheric dispersion from a ground-(
meters of that building. , ,
level gaseous source when wind direction is unchanging are estimated with
- the equation ,
-0.5(y6y) ,,2,1 X_ , 1 exp Q Ku6ygz , ,
f P
where X = the short-term average centerline value of the ground level concentration (Ci/m )' . .
- u a windspeed (m/sec) 6y = standard deviation of distribution of fluctuations in the -
i horizontal wind direction (meters)
Cz =' standard deviation of distribution of fluctuations in the
. vertical wind direction (meters) - .
y = horizontal distance perpendicular to axis of plume (meters) ,,
~
i
,f = factor of increase in atmospheric dilution caused by mixing ,
in building wake Isograms of atmospheric dispersion from a gaseous discharge from a building to a location downwind are based on the following conditions and l
t assumptions:
- 1. Each of Pasquill's atmospheric stability classes (A through G).
l t ._.. - . - - - . . . -. _ . - - . - - , . - . , - - _,_ - - . .
e .
Page 2 NUCLEAR SAFET1* ASSOCIATES i
- 2. dhastant,unchangingwinddirection.
., 3 . Short-term gaseous release (8' hours or less). -
- 4. Wind speed: one meter per second.
- 5. Boundary of atmospheric mixing is"1500. meters above ground surface.
Procedure for Estimating Atmospheric.
Concentration of Airborne Radionuclides
- 1. Estimate the release rate or quantity of airbbine radionuclides release to the atmosphere.
- 2. Read the wind speed and wind direction from the anemometer and wind vane on the plant site. .
- P (meters second , miles , 0.45 hour5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br /> .
- 3. Estimate the atmospheric stability class by observing the prevailing wear.her conditions. Choose the stability class (A, B, C, D, E, or F) on the basis of the following table & guidance.
- 4. Select the isogram ca transparent film which corresponds to the atmospheric stability class existing. ,
- 5. Superimpose the isogram on a 7.5 minute series USGS topographic map of the Castle Hayne quadrangle (scale 1.64 inch equals one kilometer)
. with the origin of the isogram at.the point of gaseous discharge to the atmosphere and the axis of the isogram in the downwind direction.
- 6. Each isopleth coincides with locations on the map where the atmospheric dispersion from the point of discharge to the receptor location is
~.
estimated to be that value written beside the isopleth. Some additional values of dispersion factors along the plume centerline are indicated on the' axis of the isogram. ' '
- 7. If the actual wind speed exceeds one meter per second, divide the dispersion factor identified with cach isopleth by the actual wind I
speed to get a better estimate of the dispersion factors.
l l
1 i
i
.Page 3 NUCLEAR SAFETY ASSOCIATES
- 8. At a steeptor location of- interest on the map, read the dispersion
, factor from "the isopleth or interpolate between the two nearest isopleths.
- 9. Estimate the atmospheric concentration of radionuclide i at the receptor location of interest with the equation Xg =q g g X Q
where: I g = atmospheric concentration (Ci/m ) of radionuclide.i ,,
q = release rate of radionuclide i to the atmosphere (Ci/sec) 3 X/Q = atmospheric dispersion factor (Ci/m;..per Ci/sec) -
Note: If qg represents the total (integrated) release of radionuclide i l to the atmosphere (in Curies) then Xg represents.the total exposure to a potential receptor (Ci . sec)/m ).
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e
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, i NUCLEAR SAFETY ASSOCIATES r
364:
+~
Y IS0 GRAMS OF PROJECTED DOSES
. DUE TO A NUCLEAR CRITICALITY s
Isograms of projected doses due to a nuclear criticality are provided separately for total body gamma dose, skin beta dose, and adult thyroid dose commitment by inhalation. Each isogram can be superimposed on the 7.5 minute series of USGS topographic maps.
The isopleths represent lines of projected ionstant dose potential (in units of REMI) at locations on the map on which they are superimposed.
~~
Ea'ch isogram matches the scale (1.64 inch equals one kilometer) of a 7.5 minute series USGS topographic map. The distances downwind where additional doses are projected to occur are marked on tha axis of each isogram.
Bases f
- 1. The conditions 'and assumptions on which the dose 'isopleths are based are: _
8
- 2. Nuclear criticality event: 1 x 10 fissions 4
- 3. Radionuclides released to atmosphere:
Nuclide Quantity Nuclide Quantity (curies) (curies)
Kr-83m . 2.68 Xe-135 12.0 . .
' Kr-85m 12. Xe-137 2800.
'Kr-85 -
1.1 x 10' Xe-138 870. . .
Kr-87 72.5 1-129 3.0 x 10' Kr-88 47. 1-13 1 0.13 .
Kr-89 2970. 1-132 .- 0.49 Xe-131m 2.8 x 10' I-133 2.5s Xe-133m 4.0'x 10 -2 1-134 35.
Xe-133 . 0.94 I-135 8.7 ,
f Xe-135m 8.0 6
+
NUCLEAR SAFETY ASSOCIATES Page 2
( -
'N
- 4. Airborna radionuclides are released to the atmosphere at ground level.
- 5. Wind speed: one meter per second (1 m/sec = 2.24 miles / hour)
- 6. Constant wind direction. '
- 7. Atmospheric stability class: Pasquill type F Procedure - - ,
- 1. Place the isogram on a 7.5 minute series USGS topog'raphis map of the Castle Hayne quadrangle (scale 1.64. inch equals one kilometer) with -
the origin of the isogram at the point of dis'ch'atget to the atmosphere
'~
and the axis of the isogram in the downwind direction.
- 2. Each isopleth coincides with locations on the map where the potential dose to a person remaining throughout the release is projected to be that written beside the isopleth.
( 3. If the actual wind speed exceeds one meter per second, divide the dose
~
identified with.each isopleth by the actual wind speed to get a better estimate of the projected doses associated with each isopleth.
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PRO"'?C"'IVE ACTIO?! CUIDES ,
Recosamended protective actions to avoid whole body and thyroid dose from espesure to a gaseous plume.
L ProjectedDose(Rem)to RecossendedActions(a) . Comuments the Pooulation No protective action required. Previously recommended l
.; Whole body <1 State may issue an advisory to seek shelter and await protective actions may further instructions or to voluntarily evacuate. be reconsidered or Thyroid <5-Monitor environnental radiation levels. terminated. . ;
Seek shelter and watt further instructions.
h ie body 1 to <5 Consider evacuation particularly for children and i pregnant women.
Thyroid 5 to <25 Monitor environmental radiation levels.
- Control access. i Conduct mandatory evacuation of populations in the feeking shelter would . ,
Whole bo % 5 and above pret t e ter.nire." area. be en alternative if '
Monitor enviro.sental radiation levels and adjust area , evacuation were not Thyroid 25 and above for mendatory evai.uation based on these levels. famediately possible.
Control access.
Projected Dose (Rem) to .
- Emergency Team Workers .
Control esposure of energency team meeers to these Although respirators hie bo% 25 levels encept for lifesaving missions. (Appropriate and sta'21e lodine should controls for esergency workers. Include. time limita- be used where effective i Thyroid 125 tions respirators, and stable todine.) to control dose to emer- -
,I gency team worters, thy-Control esposure of emergency team meeers performing roid dose may not be a lifesaving missions to this level. (Control of tia 4
Ilmiting factor for Whole body 75 lifesaving missions.
of esposure will be sost effective.) , -
- These actions are recosuended for planning purposes. Protective action decisions at the time of the l'
j incident must take into consideration the impact of entsting constraints.
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EVACUATION TIME TEV - T D
+ T N + Tg + TT -
APPR0XIMATE TIME SEGMEllT RANGE 0F 1100RS ._
T _ DECISION TIME 0.5 - 1.5 D
Tg - TIME TO NOTIFY POPULATION 0.2 - 1.0 r 0.2 - 2.0 Tg - TIME FOR MOBILIZATI0tl ,
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TOTAL 1.1 - 6.0*
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.I PROTECTIVE .TCTION GUIDES i .
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Recomunended protective actions to avoid whole body and thyroid dose from espesure to a gaseous plume.
4 Projected Dose (Rem) to RecommendedActions(a) ' Comments - -.
the Pooulation ,
.No protective action required. Previously recossended Whole body <1 State may issue an advisory to seek shelter and awatt protective actions may further instructions or to voluntarily evacuate. be reconsidered or o Thyraid 4
! <5 Monitor environmental radiation levels. terminated.
l Seek shelter and wait further instructions.
Whole body 1 to <$ Consider evacuation part1Cularly for chlidren and pregnant women.
Thyroid 5 to <25 Monitor environsental radiation levels.
Control access.
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i Whole body 5 and above preWter.nire. area. be en alternative if Monitor enviro . ental radiation levels and adjust area , evacuation were not t 3
Thyroid 25 and above for mendatory evacuation based on these levels. tamediately possible. .
Control access, 1 .
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~
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{
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- These actions are recossended for planning purgeses. Protective action decisions at the time'of the incident must take into consideration the impact of entsting constraints. ,
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