ML19327A709
| ML19327A709 | |
| Person / Time | |
|---|---|
| Site: | 07000824 |
| Issue date: | 09/29/1989 |
| From: | Christopher Boyd BABCOCK & WILCOX CO. |
| To: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 25974, NUDOCS 8910170083 | |
| Download: ML19327A709 (69) | |
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'70- BR4-RETURNL D
- babcock & WilCOX
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NNFD RESEARCH LABORATORY g
r a McDermott company l
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. Box 11165
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.y 2 6000 September 29, 1989 ny 3 4
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5 OCTo5IS89 } :-1 9
4 A'4*sh8 U.S. Nuclear-Regulatory Cor
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T Attn: Leland C. Rouse, Chief Fuel Cycle Safety Branch g
Division of Industrial & Medical Nuclear Safety Washington, D.C._ 20555
Reference:
- 1) Ltr. from C.C. Boyd to L.C. Rouse, dated May 19, 1989
- 2) Ltr. from L.C. Rouse to C.C. Boyd, dated August 8,1989 Gentlemen:
The Babcock & Wilcox Company, Naval Nuclear Fuel Division Research Laboratory (NNFD-RL), is providing for your information changes to the demonstration section of our license,'SNM-778, to reflect the recently approved changes to our organization.
An explanation of the changes is attached along with the actual page changes to our license. Revisions are indicated by a vertical line in the right hand margin of the page.
The specification section of our license, which also reflects these changes, was submitted as Reference 1 and latter approved by Reference 2.
NNFD-RL believes these changes to be an improvement to our current organization and administrative in nature.
If you should have any further questions, please feel free to contact me at (804) 522-5753.
Sincerely, f.
Charlie C. Boyd, Jr.
Licensing & Compliance Officer 1
Attachments cc:
U.S. Nuclear Regulatory Commission Region II i
Attn: Stewart Ebneter, Regional Administrator l
101 Marietta ST, N.W.
l Atlanta, GA 30323 I
D@3 1
8910170083 890929
{DR ADOCK 0700 4
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' DOCKET NO.' 'b-b2h
'CDNTROL No. -
? S W A-DATE OF D00.-
M W h 29.-l % 9 DATE RCVD.
kbherY Nk3 lFCUF 1 /
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FCAF LPDR I & E REF, !
SAFEGUARDS [
. FOTC-OTHER DATELO b)
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Attachment l
SNM-778 ORGANIZATIONAL CHANGES
- The Manager, Regulatory Relations (Manager, RR) is now called the Manager, Safety & Safeguards (Manager, SS)..
-- The Supervisor, Health & Safety is.now called the Supervisor, Health Physi cs..-
- The Industrial Safety Officer now reports to the f;NFD Health &
Safety Manager.
His responsibilities at and for the NNFD-RL remain the same.
However, the Manager, Safety and Licensing and the
' Supervisor, Health Physics are no longer directly responsible for this function.
- The Facility Supervisor and License Administrator positions are now combined-into one position (with the same functions, I
responsibilities, and requirements) called the Licensing i
' Compliance Officer.
- National Bureau of Standards (NB3) has been changed to National Institute of Standards and Technology (NIST).
- The. titles and responsibilities of Senior Health Physics Engineer and the Health-Physics Engineers are now consolidated into one title, that'of Health Physicist. There are no changes to the duties, responsibilities, and requirements.
- The Industrial Safety Officer is now a
- formal part of the Area
+
' Operating Procedure and Radiation Work Permit review process.
- The-position of Supervisor, Health Physics is held by S. W. Schilthelm.
- The-position of Licensing & Compliance Officer is held by C. C.
Boyd, Jr.
- The position of Industrial Safety Officer is held by A. J. Ambrose.
- The resumes of. the Health Physicists (T. Grochowski, D. L. Spangler, and C. P. Yates) are provided in lieu of the resume of the Senior Health Physics Engineer.
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,3 cL REVISIONS BY: PAGE' AND PARAGRAPH b;
6 Page'9
- C
- Facility Supervisor changed to Licensing 8-Compliance Officer.
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Page'10-6 Jn JParagraph:10.4.2.5-L upervisor, Health-and Safety' changed to Supervisor, Health Physics..
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- Pa ra g raph - 10.-4. 2. 6 -
' Health and Safety Group changed to Health Physics Group.
Page.10-9 Paragraph.10.5.3 Health and; Safety changed to Industrial Safety for Housekeeping and for Emergency
~
Equipment.
.Page 11-1 Paragraph'11.1.2~
-Manager,. Regulatory-Relations (Manager, RR) changed to Manager, Safety & Safeguards (Manager,SS).
The Manager, Facilities _ no longer reports to the Manager, SS.
- Paragraph 11.1.3 (was old paragraph no'.11.1.5)
Manager, RR changed to Manager,. SS.
- Health and
- Safety Group changed to Health Physics Group.
Supervisor,:. Health,and Safety changed to Supervisor, Health Physics.
License Administrator changed to Licensing & Compliance Officer.
Paragraph 11.1.4 (was old paragraph 11.1.3)
L Facility Supervisor. changed to Licensing & Compliance Officer.
' Supervisor, Health and Safety chcnged to Supervisor, Health Physics.
The Licensing & Compliance Officer now reports to the Managrr, Safety and Licensing vice the Manager, SS. ;,
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Thei responsibilities _ of. the License Administrator ~ from the old paragraph _11.1.10 L
. and;the Facility Superv sor rom old paragraph:1~1.1.12 have been added as the-third i
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-and fourth (page 11-2) paragraphs.
Page 11-2 cParagraph111.1.5 (was old_ paragraph 11.1.4)-
s
' Facility-Supervisor changed to Licensing & Compliance Officer.
?
' Supervisor; Health and Safety changed to Supervisor, Health Physics.
Paragraph 11.1.6
. Supervisor, Health and Safety changed to Supervisor, Health Physics.
Manager, RR changed to Manager, SS.
- Health'and Safety Group changed.to Health Physics Group.
' Senior Health Physics Engineer changed to Health Physicists.
The Health Physics Supervisor is no longer responsible for industrial safety.
- p ro g rams.
The -Industrial Safety Officer now reports to the -Manager, Health-and
' Safety at'NNFD.
Paragraph:11.1.7 Senior-Health Physics Engineer changed to Health Physicists.
Supervisor, Health and Safety changed to Supervisor, Health Physics.
. Health. Physics staff changed to Health Physi _cs Group.
Page 11 ~ Paragraph 11.1.7 Facility Supervisor changed to Licensing &_ Compliance Officer.
Paragraph.11.1.8 Supervisor,- Health and Safety changed to NNFD Manager, Health and Safety.
. Facility Supervisor changed to Licensing _ & Compliance Of ficer.
Page 11-4 Paragraph 11.1.8
~ Signature authority added on the Area Operating Procedures and Radiation Work
. Permits for the Industrial Safety Officer..
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- 0ld paragraph 11' 1.10 combined with' new ' paragraph 11.1.4.
E Paragraph 11.1.10'.
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The_ Nuclear Criticality Safety Officer is now appointed by the Manager, SS.
.y Page 11-51 4
Paragraph 11'.1.10l
~
' Manager, RR changed to Manager, SS.
. License Administrator changed to Licensing & Compliance Officer.
Since the License Administrator and the Facility Supervisor are combi'ned into the Licensing & Compliance.- Officer, the requirement to. discuss the. report. prior to submission has been deleted..
Old paragraph 11.1.12 combined with new paragraph 11.1.4.
Paragraph 11.1.11 Manager, RR changed to Manager, SS.
-Supervisor, Health and Safety changed to Supervisor, Health Physics.
Page-11-6~
Pa ragraph - 11.1.11 Manager, RR changed to ' Manager, SS. -
License - Administrator changed to Licensing' & Compliance Officer.
Paragraph.11.2 Within this paragraph ~ the - positions previously discussed in paragraph numbers
.11.2.3, 11.2.4, 11.2.5, 11.2.6, 11.2.7, are now discussed in paragraph numbers 11.2.7, 11.2.3, 11.2.4, 11.2.5, 11.2.6 respectively.
Paragraph 11.2.1 Under experience,'the reference to section 11.2.1 has been changed to 11.1.3.
Page 11-7 Paragraph 11.2.2 Gary S. Hoovier has been replaced by S. W. Schilthelm as Supervisor, Health and Safety (now called Supervisor, Health Physics).
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.,3-p Page 11-8'and 11-9.
- Paragraph 11.2.3-x 4'
> Reginald R. Spradlin -has _ been replaced by A. J. Ambrose as-the Industrial Safety Officer.
Page 11-11 A. F. Olsen has been replaced by. Charlie C. Boyd as the License Administrator and Facility Supervisor (now called-the Licensing & Compliance Officer).
Page 11 This;-Nuclear-Criticality Safety (NCS) Of ficer is now the Manager of the NCS group a
vice the supervisor.
The NCS group is now called a unit.
1
.Lynchburg Research Center has been changed to the NNFD-RL.
Page 11-13 through'11-16 Paragraphs 11.2.7.1, 11.2.7.2, and 11.2.7.3 The resumes of the three Health Physicists have been added.
q Page-11-16 Paragraph 11.3.1-Facility Supervisor changed to Licensing & Compliance Officer.
Page 11-17 Paragraph 11.3.1 Facility Supervisor changed to Licensing & Compliance Officer, t
Supervisor, Health and Safety changed to Supervisor, Health Physics.
The Health Physics Supervisor is no longer responsible for industrial safety 1
programs, therefore, the Industrial Safety Officer has been added to the review process. -
7 Page 11-18 Paragraph 11.3.2 Health and Safety Group changed to Health Physics Group.
l Senior' Health Physics Engineer changed to Health Physicists..
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S0pervisor,' Health and Safety changed to Supervisor, Health Physics.
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- The words, "or his designated alternate" have been added.
p Page-11-21' i
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JParagraph ll.5 :
k Figure 111-2 is referenced vice Figure 9-4.-
LFacility Supervisor changed to Licensing & Compliance, Officer.
Supervisor, Health and Safety changed to Supervisor, Health Physics.
Page 11-22
=New organization diagram.-
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v Page 11-23 Facility Supervisor changed to Licensing & Compliance Officer.
Page 12-l'.
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- Paragraph 12.1 Health and Safety changed to Health Physics.
.Pa'ragraphs.12.2,12.2.1, and 12.2.2
' Health and Safety Group. changed to niealth ~ Physics Group.
Page 12. Paragraphs 12.2.2, 12.2.3, 12.2.4, and 12.2.5
' Health and Safety Group changed to Health Physics Group.-
Page-12 ~'
Paragraph 12.2.5 (Health;and Safety Group changed to Health Physics Group.
-Page 12-4
-Paragraph 12.3.4
" Health Physics Engineer changed to Health Physicist.
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lPage 12-5 et -
1 Paragraph 12.3.4.3 r"yz
' [ Senior Health Physics Engineer changed to Health Physicist.
Health and Safety. Group changed to Health Physics Group.
- Paragraph 12.4.
5 Health and-Safety Group _ changed to Health Physics Group.
~
_ Health Physics; Engineer changed to Health Physicist.
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PageL12-6 I
~
-Paragraph 12.5-
.Hehlth and Safety Group changed to Health Pnysics Group.
Health and. Safety Supervisor audits changed to Health Physics Supervisor audits, a
Paragraph 12.6.1~
Supervisor, Health'and Safety changed to Supervisor, Health Physics.
Health and SafetyL Group changed.to -Health Physics Group.
Page'12-8.
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' Paragraph 12.6.2
- j National ~ Bu'reau = of Standards (NBS) has been changed to ' National Institute of j
. Stan'dards ' and. Technology ' (NIST).
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- Page ?l2-9 'to 12-11
-l 1
Paragraph 12.8.1.1 l
- Supervisor, Health and Safety changed to Supervisor, Health Physics.
- Page 12-12 to.12-13 Paragraph 12.8.1.2 l
Supervisor, Health and Safety changed to Supervisor, Health Physics.
-Page 12-14 Paragraph.12.8.1.3 l-Supervisor, Health and Safety chang (1 to Supervisor, Health Physics.,
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, k LParagraph 12.8.2,-
TSupervisor, Health and Safety chan'ged to Supervisor, Health Physics'.
t' eManager,' RR! changed to. Manager. - SS.
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' Paragraph ;12.8.3.1'and 12.8.3.2 THealth and' Safety Group. changed to Health Physics Group.
Page.12-16
~ Paragraph 12.8.4
- Health.and ' Safety Group. changed. to Health Physics Group.
JParagraph 12.8.5.1-l Health'and Safety Group., changed to Health Physics Group.
. Supervisor Health and-Safety changed to Supervisor, Health Physics.
i-Pa'ge 12-18.
.Pa ra graph - 12.8. 5. 2 e
Health and Safety Group changed to Health Physics Group.
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' Supervisor,l Health and, Safety changed to Supervisor, Health Physics, u Pa ge ' l'2-19 =-
' Paragraph 12.8.5.3 and 12.9
- Health'and ' Safety Group changed to Health Physics Group.
Page '2-28 1
Paragraph 12.10.2.2.2 Health'and Safety changed to. Health Physics.
Page~12-35
.: Paragraph 12.12 Health and Safety Group changed to Health Physics Group.
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Page 12 36 r;
, " Paragraph 12.12 and 12.13.1 4
f upervisor, Health and Safety ch'anged to Supervisor, Health Physics.
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- P Paragraph 12;13.1.1'
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l Health Physics Engineer changed t'o Health Physicist.
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Paragraph,12.13.2_
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- Health-and Safety. Group changed to Health-Physics Group. -
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Page 12-38 L
= Paragraph 112.'14.1 Supervisor, Health and-Safety changed to Supervisor, Health Physics.
K, Page-12-38-and 12,
l Pa ragraph.' 12.1.4.1.3' Health and Safety Group. changed to Health Physics Group.
.~Page 12-41
. Paragraph l12.14L2 Health Physics. Engineer changed to Health Physicist.
Sup3rvisor, Health and Safety changed.to' Supervisor, Health Physics.-
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Page 12 Note for-Table 12-24 Supervisor, Health and Safety changed to Supervisor, Health Physics.
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Page 12-43 Pa ragraph.12.14.3
. Health and Safety Group. changed to Health Physics Croup.
Page 13-2 p.
Paragraphs 13.2 and 13.3 Health and Safety Group changed to Health Physics Group..
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P e' 14-1
, Paragraph 14.1 l
Manager, RR' changed to Manager, SS.
v Facility Supervisor _ changed to Licensing & Compliance Officer..
License Administrator changed to Licensing a Compliance Officer.
Since the License Administrator and the Facility Supervisor are combined into the Licensing & Compliance Officer, the requirement to -discuss the report prior to :
submission has been deleted.
Page 14-8 Paragraph 14.3.2.2 Facility Supervisor changed to Licensing & Compliance Officer.
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,o" Attachm:nt s
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LIST OF REVISED PAGES
- [ Gb REMOVE ADD
- Page Rev Date Page Rev Date 9-10 0
10/85 9-10 12 9/89 10-6 9
3/88 10-6 12 9/89 10-9 S
11/87 10-9 12 9/89 11-1 4
4/87 11-1 12 9/89 11-11 4
4/87 11 12 9/89' 11-1 7
9/87 11-1 12 9/89 11-2 7
9/87 11-2 12 9/89 11-3 5
5/87 11-3 12 9/89 11-4 7
9/87' 11-4 12 9/89 11-5 7
9/87 11-5 12 9/89 11-6 7
9/87 11-6 12 9/89 111-7 to 5
5/87 11-7 to 12 9/89
.11-14
'11-14 11-15 4
'4/87 11-15 12 9/89' 11-16 4
4/87 11-16 12-9/89
+
11-17 5
5/87 11-17 12 9/89 11-18 4
4/87 11-18 12 9/89 11-20 11-20 11-21 7
9/87 11-21 12 9/89 11-22 4
4/87 11-22 12 9/89 i
11-23 12 9/89
~
12-1 to 4
4/87 12-1 to 12 9/89 12-6 12-6 12-8 to 4
4/87 12-8 to 12 9/89 12-13 12-13 12-14 7
9/87 12-14 12 9/89 12-15 4
4/87 12-15 12 9/89 12-16 4
4/87 12-16 12 9/89~
12-18 4
4/87 12-18 12 9/89 12-19 4
4/87 12-19 12 9/89 12-28 4
4/87 12-28 12 9/89 12-35 4
4/87 12-35 12 9/89 12-36 4
4/87 12-36 12 9/89 12-37
-4 4/87 12-37 12 9/89 12-38 7
9/87 12-38 12 9/89 12-39 4
4/87 12-39 12 9/89 12-41 4
4/87 12-41 12 9/89 12-42 4
4/87 12-42 12 9/89 12-43 4
4/87 12-43 12 9/89 13-2 8
11/87 13-2 12 9/89 14-1 7
9/87 14-1 12 9/89 14-8 8
11/87 14-8 12 9/89
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FIGURE 9-4 Facilities Work Order Form Ta PLANT DEMEMG Dets From
._ Sectan sir.e Sectkm W Detec Date nee *e*
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DEScRPTION OF WOR ( TO BE DOffi i
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l SIGNATlM REQUWM Industrial Safety Offken Health Physics Licensing & Compliance Officen space Below 1his Line for Plant Engineering Use Only order neceived onte w
Pianned starting o.t=
eianned compietion Date i
i order completed work order nunber
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L License No SNM 778 Docket No.70-824 Date Sept., 1989 Amendment No.
5 Revision No.
12 Page 9-10 1
l Babcock &Wilcox a McDermott company
.. A
Y fy But,1 ding J consists of.three courses of block.. The Annex is provided with exhaust-ventilation thro' ugh ducting which connects Building J:with the Annex thereby permitting.the smoke detector y
and air sampler in. Building J to serve both. The Annex is provided with a_ metal roof which is hinged to_ Building J, capable of being locked and provided with side panels which permit the
. roof to fit flush with the top of the block walls. Containers
-are-loaded into the Annex from the top. A curbing will be placed on-the approach side of the~ addition to prevent a loading ~ vehicle-from accidentally contacting the wall. 'Two individuals are involved in. loading containers'into this facility to prevent a container from striking the walls.: This facility provides storage of waste that is contaminated with irradiated fuel-and is being stored on site until it is accepted by the DOE under the Nuclear Waste Policy Act of 1982. The maximum quantity of SNM per container shall be limited to 45 grams.
10.4.2.5 The 0utside Waste Storage Area is located adjacent to Building J.
This area is' fenced, locked and paved. Waste stored in this area i
is limited to that contained in closed metal containers. Each container is. limited to not more than'a Type A quantity (10 CFR l
71.4).or 0.5 grams of fissile material or both. Pu shall not be stored in this area. Containment'of stored waste is assured by a quarterly visual inspection by the Supervisor, Health Physics.
l 10.4.2.6 The High Level Waste Storage Tubes are located adjacent to'the l
south side of the Liquid Waste Disposal Facility. -These tubes j
are constructed of two sections of iron pipe, immersed in a
concrete, and below ground level. The upper section of pipe (approximately 42-inches long) is 6-inches in diameter. The l
lower section (approximately 80-inches long) is welded to the upper section and-is 5-inches in diameter.- Each tube is fitted with a concrete-filled iron plug. These tubes are locked and under the direct control of the Health Physics Group. Waste l
~
stored in these tubes is limited to that which is produced in the Hot Cells and must be in closed metal' containers.
The quantity of fissile material permitted in each tube is limited to one unit.
10.4.2.7 The Temporary Storage Facility is located adjacent to the Reten-
]
tion Basin, within the fenced and locked restricted area (Fig.
10-1). This facility (Fig.10-3) consists of an in-ground array of eight vertical, concrete " silos" arranged in two rows of four.
The silos rest on a common concrete pad and are surrounded at the top by a concrete apron that promotes rain water runoff. Each silo is equipped with a 24-inch thick concrete lid. The lid q
License No SNM 778 Docket No.70-824 Date Sept.,1989 Amendment No.
5 Revision No.
12 Page 10-6 Babcock &Wilcox a McDermott company
~ - -, - -
l- - :L L-L --
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.i 10.5.2 Insurance Inspection _P,eports - The site is inspected twice annually:
the Arkwright-Boston ~ Insurance Company on behalf of the Mutual-l=
Atomic Energy _ Reinsurance Pool- (MAERP). The inspection reports r
list the following items in.each report; housekeeping, maint'e-
+
nance & repair, Supervision fire equipment watchmen, radioisotope handling, areas sprinklered, water supply, all-_ valves found open, criticality control, and until the decommissioning of the last J
_' reactor, nuclear reactor operation. These reports have con-K sistently-found that the site meets the requirements in each category for a " satisfactory" rating.- On a few occasions there have been. recommendations that the site add fire protection equipment when the use of an area has been changed. Each such recomendation has been addressed at the site in a manner that has
'been found acceptable to the inspectors upon their reinspection.
The reports on which the above statement is based are dated from 1977 through 1985.
10.5.3 Fire protection equipment is installed in response to recommen-dations made by the Industrial Safety Officer, the Corporate Fire Protection Engineer, or the insurance underwriters.
Installed systems are approved and inspected by Factory Mutual Engineering Association. Routine inspection and maintenance is described below:
EQUIPMENT MAINTENANCE RESP 0NSIBILITY REFERENCE Portable fire Insp./ test Industrial Safety NFPA 10 extinguishers FM 4-5--
Fire hoses Insp./ test Industrial Safety NFPA 10 Sprinklers Test Plant Engineering NFPA 13 FM 4-5 Fire suppres.
Inspection Plant Engineering NFPA 12-A systems (Halon)
FM 4-8N Mfg.
o Smoke det.
Test Plant Engineering Mfg.
Heat det.
Test Plant Engineering Mfg.
Housekeeping Inspection Industrial Safety Emer, equip.
Inspection Industrial Safety Mfg.
License No SNM 778 Docket No. 70824 Date Sept., s 1989
!(
Amendment No.
5 Revision No.
12 Page 10-9 Babcock &Wilcox a McDermott company
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TABLE OF CONTENTS'
~
Section-Page 11.0-ORGANIZATION AND PERSONNEL 11-1 11.1 SITE LINE OR@.NIZATION 11-l' 11.1.1 Vice President, NNFD.
11-1 l11.1.2
- Manager, Safety & Safeguards 11-1 11.1.3 Manager, Safety and Licensing 11-1~
- 11.1.4 Licensing & Compliance Officer...
11-1 11.1.5-Area Supervisors 11-2 11.1.6 Supervisor, Health Physics 11-2
- 11.1.7 Health. Physicists 11-2 i
11.1.8 Industrial Safety Officer 11-3 g
. 11.1.9 Accountability Specialist 11.
11.1.10 Nuclear Criticality Safety Officer 11-4 11.1.11 Safety Review Committee 11-5 1
- 11.2
. EDUCATION AND EXPERIENCE OF KEY PERSONNEL 11-6 t
L 11.2.1 Safety and Licensing Manager 11-6 l
11.2.2
. Supervisor, Health Physics 11-7 11.2.3 Industrial Safety Officer 11-8 11.2.4 Accountability Specialist 11-9 11.2.5 Licensing & Compliance Officer.
11-11 License No SNM 778 Docket No.70-824 Date Sept.,1989 5
Amendment No.
Revision No.
Page Babcock &Wilcox a McDermott company
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TABLE OF CONTENTS (Continued)
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--Section-Page.
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-11.2.6 Nuclear Criticality Safety Officer 11 j
- 11. 2. 7.
Health Physicists.
11-13' 11.3-
~ PROCEDURES
.- 11a16-
'11.3.1
~ Area Operating Procedures ( A0P)
. 11-16 11.3'.2 Technical Procedures..-
11-18 11.4 TRAINING.
11-18 11.4.1 General Radiation Protection Training 11-18 11.4.2 Program 1;.
11-19
-11.4.3 Program 2'.
11-19 m
-11.4.4
. Program 3.
. 11-19 11.4.5 Respiratory Protection Training
. 20 11.5 FACILITY CHANGE,
11-21 List of Figures Figure Page 1-LINE ORGANIZATION 11-22 11-2 FACILITY WORK ORDER FORM.
11-23
~ icense No SNM 778 Docket No.70-824 Date Sept.,1989 L
5 Amendment No.
Revision No.
Page Babcock &Wilcox a McDermott company er s
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11.0 ORGANIZATION AND PERSONNEL i
11.1-SITE ORGANIZATION 11.1.1 ~ LVice President, NNFD - The Vice President, NNFD is responsible for ensuring that. all operations _ on site are conducted safety and in full compliance with NRC requirements.
11.1.2' The Manager. Safety & Safeguards (Manager, SS) - The Manager,- SS is
(
responsible for the safety of site operations. The Manager, Safety and Licensing reports to him.
I 11.1.3 Manager, Safety and Licensing - The Manager of Safety and Licensing is appointed by and reports to the Manager, SS. He is responsible l
for the proper management of the materials accounting function, licensing function, nuclear criticality safety function, and the Health Physics Group. He manages the allotment of. funds and other l
resources and assures the proper assignment of personnel priorities.
The Supervisor, Health Physics, Accountability Specialist, Nuclear Criticality Safety Officer, and Licensing & Compliance Officer, report to him.
11.1.4 Licensing & Compliance Officer - Research and development work at l
the site will be performed by personnel who do not report to the Manager, SS. Therefore, the positions of Licensing & Compliance l
. 0fficer and Area Supervisor have been established to control the workers and their activities.
The Licensing & Compliance Officer shall report to the Manager,
- Safety and Licensing. He shall be responsible for the safety of all operations performed pursuant to License SNM-778.
He shall utilize the expertise of the Supervisor, Health Physics, the l
Accountability Specialist, Nuclear Criticality Safety Officer, and the Industrial Safety Officer to ensure the' safety of operations.
The Licensing & Compliance Officer is also responsible for
[.
administering the license.
He is the primary liaison between the site and the NRC and other federal, state, and local agencies regarding nuclear matters.
He is the coordinator of the Safety l
Review Committee and Chairmare. of the Safety Audit-Sub-committee and represents site management on both. The Licensing & Compliance Officer is responsible for ensuring that corrective action is taken in response to audit findings as they pertain to licensed activities.
L License No SNM-778 Docket No.70-824 Date Amendment No.
Revision No.
Page Babcock &Wilcox l-a McDermott company e
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' ' c, The Licensing & Compliance Officer shall: review and have' approval-f y-
. authority for Area Operating Procedures. He shall have. authority '
g to terminate any operation-that he deems contrary to= license con-ditions. Area Operating Procedures, or-general safety conditions.
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The Licensing-A Compliance Officer shall become familiar with all L
license conditions and procedures concerned with radiation safety.
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- nuclear safety, industrial safety, and nuclear materials safeguards.
i He may consult with the following personnel to ensure compliance -
with all safety regulations and principles:
Supervisor,-Health Physics Nuclear-Safety Officer Industrial Safety Officer Accountability Specialist 11.1.5 Area Supervisors - Area Supervisors are selected by their Division Management and shall be jointly approved by the Licensing & Compli-ance Officer and the Supervisor, Haalth Physics. ~ Area Supervisors functionally report to the Licensing & Con;pliance Officer and are responsible for the safe performance of all activities in their
,f assigned area and that all activities within their assigned areas-are performed in full compliance with the license.
11.1.6 Supervisor, Health Physics - The Supervisor of Health Physics is appointed by=the Manager, SS and reports to the Manager, Safety and Licensing. The Supervisor directs the overall operation of the Health Physics Group.
He also serves on the Safety Review l
Committee. - He has the authority to stop any operation that he believes is contrary to accepted safety practices, or license requirements. The Supervisor has overall responsibility for the shipment and receipt of licensed material. and exercises signature authority on all Area Operating Procedures. He performs audits of the site.for compliance with Health Physics rules. The Health Physicists report to him.
11.1.7 Health Physicists - The Health Physicists report to the Super-visor, Health Physics. They administer the activities of the Health Physics Group, which include:
1.
Performing area surveys 2.
Administering the air sampling program
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3.'lAdministeringtherespiratoryprotectionprogram 4.
Administering the bioassay program:
5.-
Leak testing-radioar.tive sources -
L6.
Supervising shipping' and receiving of licensed material -
7.
Supervising and coordinating the waste disposal program-
~8.
Assisting in personnel, equipment, and facility decontamination.
- 9. - Conducting radiation safety-training 10.
Providing expertise in all aspects'of radiation ~ protection 11.
Generating, maintaining and distributing records and reports that are. required by NRC regulations or Health Physics procedures 12.
Providing expertise in health physics to the Licensing &
Compliance Officer.
11.1.8 Industrial-Safety Officer - The Industrial Safety Officer reports to the NNFD Manager, Health and Safety.
His responsibilities l
include the following:
l'. ' Administering the industrial safety program 2.
Reviewing proposed facility-changes to ensure fire safety 3.
Providing expertise in fire prevention to the Licensing &
b Compliance 0/ficer and the Safety Review Comittee 1:
l 4.
Performirg tests, maintenance, and inspection of fire protection, control, and extinguishing equipment-l S.
Providing training for the site Fire and Rescue Team and off site support agencies 6.
Inspecting all areas of the site periodically to ensure:
a.
Proper storage and use of flammable-solvents b.
Proper placement of fire extinguishing equipment
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Elimination of_ fire hazards
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Reduction,,to the extent practicable, of the accumulation I
of flammable materials e
- Proper use and maintenance of' electrical equipment.
l 7.. Working lwith Area. Supervisors to formulate safety rules and elimination of hazards s
8.t Linvestigation of all personnel injuries
.9.
Keeping management informed concerning industrial safety -
activities 110. Conducting industrial safety training.
- 11. Signature authority on all new or r. vised Area Operating Procedures and Radiation Work Permits (RWP's).
11.1.9 Accountability Specialist - The Accountability Specialist reports to the Manager, Safety and Licensing..He is responsible for the
- maintenance and retention of SW accot.r,tability records. He prepares and transmits the reports required by regulation to inform regulatory agencies of SW transactions.
11.1.10 Nuclear Criticality Safety Officer - The Nuclear Criticality Safety Officer is appointed by the Manager, SS and reports to the Manager, l
.1 Safety and Licensing. The Nuclear Criticality Safety Officer is responsible for ensuring that no operation at the site can lead to the inadvertent assembly of a critical mass.
To help assure this, be has signature authority for all.new Area Operating Procedures-1
..and changes to these' procedures, he obcerves operations, institutes
+
educational programs if and when he deems them necessary, and -
carries out confirming nuclear criticality safety calculations.
i The Nuclear Criticality Safety Officer will inspect all site oper-1 ations where special nuclear material is being processed, quarterly.
Other areas may be inspected less frequently, but all licensed fa-4 cilities will be inspected at least twice a year. He will consider area operations when scheduling these inspections and will, if y
necessary, schedule his inspection at more freque.it intervals.
Is L
consideration should include inspection of new operations, an audit of nuclear safety records, a check for area posting, a review of
^
current practices and a review of corrective actions recommended during previous audits and the status of the recommended actions, li
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He shall submit a report of his finding to the Manager, SS, with a copy to the Licensing & Compliance Officer.
The following i
information is to be included:
l l
1.
Areas visited l
2.
Operations observed 3.
Unsafe practices and situations noted 4.
Nuclear safety activity of the quarter 5.
Recommendations.
l 11.1.11 Safety Review Comittee - The Safety Review Comittee (SRC) shall f
be comprised of at least five technically trained and experienced members appointed by the Manager, SS.
One member shall be selected by the Manager SS to be the SRC Chairman.
The Chaiman shall preside at the meetings and keep the minutes. The Manager, SS shall appoint an Alternate Chaiman who shall act for the Chaiman during absences. One member shall be appointed by the Manager, SS l
to be the SRC Coordinator.
The Coordinator shall represent site i
management on the SRC, set the meeting agenda, and maintains the pernavit files of the Committee.
lhe SRC membership siiall have expertise in chemistry, nuclear physics, health physics, and the safe handling of radioactive material. The SRC membership shall have a general understanding of nuclear criticality safety as it pirtains to site operations.
Consultants with special expertise are available to the Comittee when needed.
The SRC shall meet at least four times a year. A quorum shall l-consist of a simple majority of the membership including the Chairman. The SRC shall review and approve all Area Operating l'
Procedures.
It shall review and approve new projects that utilize licensed material that are significantly different from previously l
reviewed and approved projects.
The SRC shall review the annual p
report issued by the Supervisor, Health Physics which summarizes l
l site workers' exposures, environmental releases, and a summary of the ALARA program accomplishments. The SRC Chaiman shall forward the Comittee minutes to the Manager, SS, with copies to the Vice l
President, NNFD and the SRC Coordinator.
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The Manager, SS rhall appoint the members of the Safety Audit Sub-l comittee (SAS). The SAS shall be comprised of at least two individuals, one of whom shall be designated as Chairman and he
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.shall report to the Chairman, SRC. The SAS shall audit site oper-l ations at least three times anrually, with successive audits separated by at least two months. Additional audits may be performed at any time. The SAS Chaiman shall develop the audit report and submit it to the SRC Chaiman. The SRC Chairman shall submit the audit report to the Manager, SS with appropriate coments, with a copy to the Licensing & Compliance Officer..
11.2 EDUCATION AND EXPERIENCE OF KEY PERSONNEL r
11.2.1 Safety and Licensing Manager - Richard L. Bennett Education:
B.Ch,E. - Che'nical Engineering, University of Delaware,1958 Experience:
(1985-Fresent) Babcock & Wilcox, Manager, Safety and Licensing, NNFD Research Laboratory, Lynchburg, Virginia.
See Section 11.1.3 l
(1982-1985)
Babcock & Wilcox, Manager, Building C Decommissioning, Lynchburg Research Center, Lynchburg, Virginia He was responsible for decontaminating facilities that were used for preparation of experimental quantities of nuclear fuels containing plutonium.
(1973-1982)
Babcock & Wilcox, Supervisor, Process Technology Group, Lynchburg Research Center, Lynchburg, Virginia This group was responsible for long-range studies, design assistance, start-up assistance, and preparation of enviroamental reports and safety analyses related to nuclear fuel conversion.
Some of the specific projects performed by the group were prepa-ration of the designs for a low-enriched nuclear fuel conversion plant, preparation of a conceptual design for a spiked nuclear fuel fabrication plant, process engineering assistance to nuclear fuel L
conversion plants, development of a halide volatility scrap L
recovery process, development of alternative effluent treatment i
systems for various nuclear fuel conversion processes, and evaluation of fabrication methods for advanced fuels.
Lloense No SNM 778 Docket No.70-824 Date Sept. 1989 Amendment No.
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i (1971-1973)
Babcock & Wilcox, Senior Research Engineer, Lynchburg Research Center, Lynchburg, Virginia I
He was responsible for the conceptual design of a facility to treat the effluent from a nuclear fuel plant and developing and evaluating processes for recovering t>yproducts from B&W wastes.
(1959-1971)
American Cyanamid Company, Process Engineer, Piney l
River, Virginia He has had broad experience in chemical engineering. This includes research ano development, designing equipment and processes, testing and operating new equipment, pilot plant operation, process i
engineering, and economic evaluation.. He has specific knowledge in pigment manufacture, effluent treatment, and byproduct recovery.
Professional Affiliations:
American Institute of Chemical Engineers (Member)
American Nuclear Society (Member) 11.2.2 Supervisor Health Physics - Steven W. Schilthelm l
Education:
B.S. - Nuclear 2ngineering, University of Wisconsin, Madison,1983 M.S. - Health Physics, University of Wisconsin, Madison,1985
- Domestic & International Shipping of Radioactive Material.
Experience:
(1985-Present)
Babcock & Wilcox, Senior Health Physicist, NNFD Research Laboratory, Lynchburg, Virginia Mr. Sch11thelm is responsible for administering the Health Physics Program at the NNFD Research Laboratory. His duties include external and internal exposure control, shipping and receiving of radioactive material, maintaining the respiratory protection pro-gram, preparation and presentation of radiological safety training courses, maintaining the support for licensed activities.
Mr. Schilthelm is the Emergency Radiological Safety Officer and is the designated alternate for the position of Supervisor, Health and Safety.
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I" (1984-1985) Research Specialist, Synchrotron Radiation Center, University of Wisconsin, Madison, Wisconsin Mr. Schilthelm was responsible for Radiation Surveys and subsequent Shielding calculations and design at the 800 Mev electron acceler-ator/ storage ring. He co-authored a shielding upgrade proposal i
that was presented to the National Science Foundation, and he pro-vided the experimental basis for the proposal. Mr. Schiltheim i
presented a paper at the 1985 Health Physics Society meeting, en-titled " Radiation Sury2y Measurements at the Aladdin Synchrotron 1.ight Source."
Professional Affiliations American Nuclear Society (Member)
Health Physics Society (Member) l 11.2.3 Industrial Safety Officer - Anthony J. Ambrose.
l j
EDUCATION:
M.S. - Safety Management West Virginia University,1989 i
~ 8.S. - Physical Education & Health Education, West Virginia Uni-versity, 1988 Continuing Education and Certifications:
- FEMA Certified Hazardous Material Incident Analysis. West l
Virginia University,1989 r
- EPA Certified Asbestos Abatement Supervisor, West Virginia University, 1989
- EPA Certified Asbestos Abatement Worker, West Virginia University, 1989
- Red Cross Certified CPR Instructor, West Virginia Uni-versity, 1987
- Red Cross Certified Advanced First-Aid, West Virginia University, 1987
- Red Cross Certified Water Safety Instructor West Virginia University, 1986
- Weirton Heights Rescue School, Weirton, West Virginia,1986 Experience:
(1989-Present) Babcock & Wilcox, Industrial Safety Officer, NNFD Research Laboratory, Lynchburg, Virginia Se pt., 198)
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Mr. Ambrose is the NNFD-RL's Industrial Safety Of ficer. He is I
i responsible for compliance with the regulations of the Occupational l
Health and Safety Administration. He advises the NNFD-RL on the l
j standards and requirements of the National Fire Protection Associ-l ation and performs reviews of equipment and systems for compliance with NFPA standards. He performs inspections of facilities and equipment for fire protection purposes. He reviews facility changes and modifications to ensure fire safety. Mr. Ambrose l'
t performs tests, maintenance, and inspection of fire protection, control and extinguishing equipment. He is responsible for inves-tigating all accidents, and keeping his management informed of safety activities.
He performs fire and rescue training for the members of the NNFD-RL's Fire and Rescue Team, and serves as the l
Captairs of the team.
1 (1988-1989)
West Virginia University, Safety & Induttrial Hygiene Assistant / Graduate Assistant. W.V.U.
Environmental Health & Safety Department, Morgan-town, West Virginia l
Responsible for assuring a healthy and safe working environment for employees of West Virginia University.
Duties included: data base development, legislation / compliance, inspections / audits, environ-mental monitoring; air, bulk and noise sampling, training develop-p ment and implementation.
(1988-1989)
Monongalia County Schools, Substitute Teacher, Morgantown, West Virginia c
Responsibilities included classroom supervision at the elementary and high school levels, training development and implementation utilizing educational strategies.
Professional Affiliations:
American Nuclear Society (Member) 11.2.4 Accountability Specialist - Kenneth D. Long Education:
Graduate - White Sulphur Springs High School,1958 Certificate - Bookkeeping, Central Virginia Community College,1983 Experience:
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Babcock & Wilcox, Accountability Specialist NNFD Research Laboratory, Lynchburg, Virginia Mr. Long, as the Accountability Specialist, is responsible to the Manager of Safety and Licensing for the accurate accounting of all Special Nuclear, fource, and Byproduct material at the NNFD-RL.
He is responsible for recording all transfers of SNM that are made within the NNFD-RL and for preparing the reports and records of off l
site transfers.
He prepares all NRC/ DOE 741 Transaction Foms.
He is responsible for the timely completion of inventories of licensed material.
He initiates the paper work required for all shipments of licensed material.
}
In addition to his normal duties he is a Docuent Custodian.
In i
this capacity, he is responsible for the safe storage of all
^
classified DOE and D0D documents at the NNFD-RL. He is also an authorized classifier and an authorized courier of classified material.
(1970-1974) Babcock & Wilcox, Shipping & Receiving Clerk Lynchburg Research Center, Lynchburg, Virginia i
Mr. Long was responsible for the shipment and receipt of all t
materials at the LRC. This t.ssignment included the processing of all the necessary forms and doesnents used for shipping and receiving licensed materials as well as the many items that are required for operation of a research and development laboratory.
(1967-1970) Babcock & Wilcox, Technician Lynchburg Research Center, Lynchburg, Virginia Mr. Long was a technician in the Plutonium Development Laboratory during this period. He performed chemical operations utilizing Oranitsn and plutonium materials and es responsible for the i
accountability of SNM materials into and out of his area.
Professional Affiliations:
l Institute of Nuclear Materials Management (Senior Member) f American Nuclear Society, Virginia Chapter (Member)y)
Nuclear Materials Control Consnittee. B&W (Secretar i
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I 11.2.5 Licensing & Compliance Officer - Charlie C. Boyd Education:
i B.S. - Physics, U. S. Naval Academy,1976
]
Nuclear Criticality Safety Short Course,1987 l
Nuclear Criticality Safety Workshop,1986 i
Professional Certification:
Professional Quality Assurance Auditor,1989 Experience:
(1989-Present)
Babcock & Wilcox, Licensing & Compliance Officer, NNFD Research Laboratory Lynchburg, Virginia Responsible for coordination cf all licensing activities at the NNFD Research Laboratory and for the regulatory compliance auditing system at NNFD.
i (1987-1989)
Babcock & Wilcox, Licensing & Compliance Officer, NNFD, Lynchburg, Virginia Responsible for coordination of all licensing activities at NNFD and for the establishment of a regulatory compliance auditing
~,
system.
(1986-1987)
Babcock & Wilcox, Nuclear Safety & Licensing Officer, NNFD, Lynchburg, Virginia Responsible for nuclear criticality safety and coordination of all licensing activities for NNFD.
(1985-1986)
Babcock & Wilcox, Lead Engineer, NNFD, hnchburg, Virginia Responsible for the development of process and production of control rods for NNFD's Advanced Reactor Development Section.
l (1984-1985)
Babcock & Wilcox, Lead Engineer, NNFD, Lynchburg, Virginia Developed processes and procedures for fuel preassemblies within NNFD's Advanced Reactor Development Section.
1 Sept., 1989 L
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r (1976-1984)
Officer, U. S. Marine Corps
{
Held positions ranging from Platoon Comander to Marine Amphibious Brigade Comunications Electronic Officer. Responsibilities ranging from planning, coordinating, deploying, and operating comunications assets of a Brigade size task force involving local and world-wide comunications to planning and coordinating military and high school testing for the state of South Carolina, fourteen counties in Georgia, and the Panama Canal Zone.
t 11.2.6 Nuclear Criticality Safety Officer - Francis M. Alcorn Education:
B.S.
- Nuclear Engineering, North Carolina State College,1957 M.B.A - Business Administration, Lynchburg College,1974 L
- Graduate study in Nuclear Engineering, University of Virginia Experience:
(1971-Present)
Babcock & Wilcox, Manager, Nuclear Criticality l
Safety Group, NNFD Research Laboratory, Lynchburg, Virginia This unit is the Company's central organization which provides I
guidance, develops and validates the analytical methods needed 1
for criticality evaluations, does_ criticality calculations, i
perfoms nuclear safety audits. and gives assistance to the various divisions of the Company and the Company's customers in matters related to nuclear criticality safety.
In addition to his responsibility as manager of this group, he is the Nuclear Safety Officer for the NNFO-RL.
(1969-1971) Babcock & Wilcox, Criticality Specialist, Nuclear Safety Engineer, Lynchburg Research Center, Lynchburg, Virginia Transferred to the LRC as Nuclear Criticality Safety Specialist for Babcock & Wilcox's Naval Nuclear Fuel Plant Comercial Nuclear Fuel Plant, anc! the LRC.
He was appointed Nucicar Safety Officer for the LRC, (1964-1969) Babcock & Wilcox, Power Generation Division, Lynchburg, Virginia License No SNM 778 Docket No.70-824 Date Sept.,1989 Amendment No.
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I Mr. Alcorn was a physicist in the PWR Development Section and was l
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responsible for determining the most economical method for i
utilizing plutonium as a recycle fuel in B&W's pressurized water reactor concepts.
In addition, he was Nuclear Criticality Safety Advisor to the Company's Naval Nuclear Fuel Division.
(1961-1964) Babcock & Wilcox, Nuclear Power Generation Division Lynchburg, Virginia l
He has been concerned with core neutron physics analysis and design of the Consolidated Edison Reactor, the Liquid Metal Fuel Reactor, the Babcock & Wilcox Test Reactor, the Advanced Test i
Reactor, the Heavy Water-Organic Cooled Reactor Concept, and Babcock & Wilcox Pressurized Water Reactor Concepts. He developed methods for and performed calculations for criticality, fuel depletion, nuclear safety coefficients, power profiles, nuclear fuel costs and critical experiment analysis. He has also worked in the areas of kinetic safety analysis.
l l
(1957-1960) Babcock & Wilcox, Atomic Energy Division Lynchburg, Virginia He functioned as a nuclear engineer doing both core neutron physics and shielding calculations.
(1960-1961) General Nuclear Engineering Corporation, Staff Physicist Mr. Alcorn engaged in core neutron physics design and analysis of the Boiling Nuclear Superheat Reactor.
He also wrote physics articles for Power Reactor Technology which were published by GNEC for the AEC.
Professional Affiliations:
t Sigma Pi Sigma (Member)
Tau Beta Pi (Member)
American Nuclear Society - Past Chairman of ANS Nuclear Criticality Safety Division i
- Member Standards Subcommittee ANS-8.
11.2.7 Health Physicists 11.2.7.1 Health Physicist - Carl R. Yates 4,
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o Education:
B.S. - Biology, University of Pittsburgh,
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Johnstown, Pennsylvania,1979 M.S. - Biology, West Virginia University.
Morgantown, West Virginia,1981 Additional Training
" Radioactive Sample Analysis,"
Gaithersburg, Maryland,1989 i
" Environmental Radiation Surveillance,"
Boston, Massachusetts,1983.
Experience:
(1988-Present)
Babcock & Wilcox, Health Physicist, i
NNFD Research Laboratory Lynchburg, Virginia r
r Mr. Yates is responsible for tracking and reviewing the Personnel Dosimetry records of the NNFD Research Laboratory employees, en-i suring all health physics instruments are calibrated accurately l
and in a timely manner, and managing the environmental monitoring i
program.
Additional-responsibilities include preparation of health physics technical procedures and various radiation work pennits.
(1986-1988)
Science Applications International Corporation l
(SAIC), Radiological Scientist, Rockville.
Maryland l
l Mr. Yates was responsible for the on-site categorization of fuel pool-stored components for compliance with 10 CFP. 61, scaling factor detennination, and studies involving the behavior of radioiodine-in sampling lines at operating power stations.
l Additional responsibilities included writing the quality control' data report for the radiological laboratory, and acting as Project Manhger for the EPA and NIST intercomparison prograias.
L (1981-1988)
NOS Corporation, Envircamental Scientist /Pr0 ject Managee, Gaithersburg, Marylana and Pittsburgh, Pennsylvania j
Mr. Yates was responsiu. for conducting on-site environmental s9rveyr for several Department of Energy sites as 3 member of the DOE /NIG Environmental Survey Team, writing annual aeports for various nuclear power plant's environmental moaltering yograms, License No SNM 778 Docket No.70-824 Date f 9pt.,1989 t
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l writing technical procedures, sample collection auditing, and preparing the environmental study plan for a candidate high-level nuclear waste repository site.
Professional Affiliations:
American Nuclear Society (Member)
Health Physics Society (Member) 11.2.7.2 Health Physicist - David L. Spangler Education:
B.S. - Biology, Core Study - Health Physics / Nuclear Science Engineering, Virginia Polytechnic Institute and State University, Blacksburg, Virginia
- Radioactive Material Shipping Regulatory Awareness
- Contamination and Hot Particle Control.
Experience:
(1988-Present)
Babcock & Wilcox, Health Physicist NNFD Research Laboratory, Lynchburg, Virginia Mr. Spangler is responsible for administering and implementing the Health Physics Program at the NNFD-RL.
His duties include shipping and receiving radioactive material, shipping low-level waste, developing and implementing programs and procedures for; external exposure, contamination control, area surveillance, and instrtnent calibration.
(1982-1988)
Health Physicist, H. B. Robinson Nuclear Power Plant. Hartsville, South Carolina Mr. Spangler was responsible for developing and implementing rad-waste, volune reduction and shipping programs and procedures.
He was responsible for training and supervising waste processing and i
pact: aging groups. Mr. Spangler's other dutics included: area i
surveys, radiation work permits, ALARA programs, instrument cali..
bration and technical trair.ing ind qualification programs.
1 Professional Affiliation:
l A
American Nuclear Society (Member)
Health Physics Society (Member) y License No SNM 778 Docket No.70-824 Dato Sept. 1989 Amendment No.
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u 11.2.7.3 Health Physicist - Teofil Grochowski I
Education:
B.S. - Nuclear Medicine Technology, University of Virginia Medical Center /Lynchburg College,1986 Certificate in Nuclear. Medicine Technology, University of Virginia Medical Center,1985 B.S. - Biochemistry, lynchburg College,1985 A.S. - Science, Central Virginia Coninunity College,1983 i
Experience:
i (1986-Present) Babcock & Wilcox Health Physicist, NNFD Research Laboratory, Lynchburg, Virginia Primary responsibilities include administration of the respira-
)
tory protection program, bioassay program, radiation safety training of new employees, technical procedure development, pre-l paration of radiation work permits, and instrument calibrations.
Also appointed as the alternate site Radiological Safety Officer.
.)
Professional Certification:
Certified Nuclear Medicine Technologist Nuclear Medicine Technology Certification Board Registered Technologist, Nuclear Medicine American Registry of Radiologic Technologists Professional Affiliations:
l Health Physics Society (Plenary Member) l Society of Nuclear Medicine ( Associate Member)
Virginia Chapter, Health Physics Society (Member) i Virginia Chapter, knerican Nuclear Society (Member)
Virginia Society for the Advancement of Nuclear Medicine (Member)
Virginia Academy of Science (Member)
Society of Nuclear Medicine (Technologist Memter) 11.3 PROCEDURES 11.2.1 Area Operating Procedures (AOP) - All operations with licensed 1dterial Khall be conducthd in OCCord0r.(e with Area 0,'erating ProceJures or d Radiation Werk Permit. Area (nerating Procedures are prepered by any te*hnically competant per2Wh The proposed procedure is delivered to the Licensing & Complf ance Of ficer wo l
Sept. 989 Wo nes No SNM 778 Docket No. 70824 Date 5
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ensures that the procedure is in the proper format. The Licensing I
& Compliance Officer routes the procedure to the Nuclear Criticality l
Safety Officer who reviews it to assure that any nuclear criticality i
safety issues are properly addressed.
If the Nuclear Criticality
)
Safety Officer has additions or corrections, he notes them on the procedure and forwards it to the Supervisor, Health Physics.
If l
j the Nuclear Criticality Safety Officer approves it, he signs, the procedure in the space provided and forwards it to the Supervisor, Health Physics.
The Supervisor, Health Physics reviews it for l
l proper radiological content.
If he has additions or corrections, he notes them on the procedure and forwards it to the Licensing &
l Compliance Officer.
If the Supervisor, Health Physics approves the procedure, he signs the procedure in the space provided and forwards it to the Licensing & Compliance Officer. The Industrial Safety Officer reviews it to assure that any industrial safety issues are t
properly addressed.
If.the Industrial Safety Officer has additions or corrections,- he notes them on the procedure and forwards it to the Licensing & Compliance Officer.
If the Industrial Safety l
Officer approves it, he signs the procedure in the space provided and forwards it to the Licensing & Compliance Officer.
The Licensing & Compliance Officer reviews it for general safety and determines its impact on other work and facilities. The Licensing
& Compliance Officer is responsible for resolving all additions or changes recommended by the previous reviewers. When the procedure is approved by the four reviewers, the Licensing & Compliance Officer forwards it to the Safety Review Comittee. The Safety Review Comittee (SRC) may approve the procedure as written, approve the procedure conditionally with specific changes to be made prior to issuance or the SRC can disapprove it.
The SRC co-ordinator signs for the SRC when approval is voted. The procedure may be implemented subsequent to SRC approval.
Revisions to AOP's will follow this same approval route, except that the revised procedure may be implemented after receiving the approval signatures of the Nuclear Criticality Safety Officer, Supervisor Health Physics, Industrial Safety Officer and the Licensing & Compliance Officer. The revised procedure will be placed on the agenda for the next regularly scheduled meeting of the SRC. AOP manuals shall t'e placed in areas where the procedbres apply.
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1 11.3.2 Technical Procedures - Technical procedures provide detailed tech-1 nical standards and instructions for performing specific tasks.
Pursuant to this license application, they are not intended for use by operations personnel and are not distributed in the same manner as A0P's. Neither are they necessarily approved by the Safety Review Connittee.
Technical procedures for the Health Physics Group and the Nuclear Criticality Safety Group are reviewed and approved by a Health l
Physicist and the Nuclear Criticality Safety Officer, respectively, or by their designated alternates.
The distribution list for each procedure is specified in the procedure.
.11.4 TRAINING 11.4.1 General Radiation Protection Training The site provides three training programs covering the nature, use and control of radiation, and radioactivity.
These courses are presented to ensure that all site personnel receive training appropriate to their activities and to fulfill obligations under the NRC license to provide such training.
The courses consist of a series of lectures intended to present the i
proper background and technical base to allow workers to understand the principles of radiation safety.
The Supervisor, Health Physics or his designated alternate administers the course and, in general, teaches each course. Where practical, basic general procedures and federal regulations are included and discussed. Training aids, I
such as motion pictures and self-study materials, are used as l
appropriate.
i Program 1 is intended for site workers and non-site workers who will be authorized access to the restricted area. Program 2 is intended for site and non-site workers who may enter the restricted and controlled areas but who will not be permitted to work with licensed material without supervision, Program 3 is intended for authorized users (those who will be authorized to work with. licensed material and to supervise such work).
Training in area operating procedures and special area prxedures il the responsibility of the Area Supervisor. This training should be accompanied with appropriate fomal and on-the-job training as the job reqJirements dictate.
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l Llosnee No SNM478 Docket No. 70 824 Dats 12 11-18 Amendment No.
Revision No.
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i 11.4.2 Program 1 This course is presented to site workers and non-site workers who will be granted access to the restricted area but who will not be granted unescorted access to the controlled areas. The course pro-vides an introduction to radiation and radioactivity (understand-l able to a non-technical person) and a thorough coverage of safety rules and procedures, including the site emergency procedures.
Subjects include the types of radiation, ALARA, radiation effects on humans, decontamination procedures, radiation exposure to females, warning signs, basic health physics rules, a history of radiation protection, worker's rights and responsibilities, and health physics terms.
11.4.3 Program 2 This course is presented to site workers and non-site workers who will be granted unescorted access to the restricted area and con-trolled areas but who will not be pemitted to work with radioactive materials. without supervision.
This course is intended to provide the workers with a knowledge of the hazards of working in radiation and controlled areas and ways to minimize their dose. Subjects include types of radiation, radiation exposure limits, ALARA, per-i sonnel dosimetry and its use, dose calculation, biological effects.
t radiation exposure to females, radiation protection measures, warn-ing signs and labels, radiation work pemits, emergency procedures, rights and' responsibilities of workers, and health physics terms.
j 11.4.4 Program 3 This course is presented to site workers and non-site workers who
[
will be granted unescorted access to the restricted area and con-l l
trolled areas and will be permitted to work with radioactive materials and supervise such work.
This course is intended for meeting the requirements for designation of a worker as an author-ized user.
Subjects include fundamentals of radiation, external and ir,ternal radiation protection, biological effects, radiation l:
detection, instrunentation, cor,tamination control, license require-l wats, site organization, rights and responsitilities under 10 CFk L
19, ALARA. dose calculation, personnel dosimetry requirements (no l-use, posting cod labeling, and health physics terms.
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License No SNM478 Ddst No.70-824 Date l
2 11-19 Amendment No.
Revision No.
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L, 11.4.5 Respiratory Protection Training Training in respiratory protection techniques will be required of j
all workers before.the use of such equipment will be allowed. This training will be carried out by a qualified individual, as defined l
in NUREG-0041 (Section 12.1), who will document that such training as been completed. Those persons who direct the work of workers l
using respiratory protection will be included in the trairsing courses. Biennial retraining will be scheduled, at the discretion of the qualified individual, to ensure that a high degree of pro-ficiency in the use of respiratory protective devices is maintained.
{
Training in respiratory protection shall include the following subjects:
a.
Discussion of the airborne contaminants present in the work environment including their physical properties, physiological actions, toxicity, means of detection, and maximisn permissible l
concentrations (MPC's).
i L
b.
Discussion of the importance of selecting the proper respirator i
based on the hazard and the dangers of using respirators for a purpose other than that intended, i
c.
Discussion of the construction, operating principles, and limitations of the available respirators.
d.
Discussion of the use of engineering controls as a substitute for respiratory protection and the need to make every reason-able effort to reduce or eliminate the need for respiratory protection.
e.
Instruction in methods to be used to determine that the respirator is in proper working order.
f.
Instruction in fitting the respirst9r properly, field testing for preper fit, and facto.'s thet may influence a proper fit.
9 Instructions in the pmeer ut,e 6nd maintenance of the respirater.
h.
Discussion of the uses of various cartridges and canisters available f or air-purifying respiratorse Sept. 1989 License No SNM 778 Docket No. 70 824 Date 5
la 11-20 A, ne No.
noi.i.n No.
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Review of radiation and contamination hazards, including a review of other protective equipment that may be used with respirators.
.]
j.
Instruction in emergency actions to be taken in the event of f
respirator malfunction.
i
~k.
Classroom instruction to recognize and cope with emergency situations while working with a respirator, l.
Any additional training as needed for special use.
m.
The wearer must pass a written examination on the material presented on respiratory protection.
11.5 FACILITY CHANGE Changes and modifications to buildings, exhaust ventilation systems, gas supply systems, emergency electrical systems, etc. are requested on Form RL-229, " Facilities Work Order Form" (Figure 11-2). All work l
orders are forwarded to the maintenance supervisor. The Plant Engi-f neering Supervisor determines if the request involves a facility change.
If a facility change is involved, the work order is forwarded to the Licensing & Compliance Officer.
It is the Licensing & Compli-i ance Officer's responsibility to determine that all safety and licensing considerations have been addressed and if the request must t
be approved by the Safety Review Comittee.
Space is provided on the form for the approval signatures of the Supervisor Health Physics, r
the Industrial Safety Officer, and the Licensing & Compliance Officer.
Completed forms are kept on file by the maintenance supervisor and are audited once a month by the Health Physics Group.
i I
Ucense No SNM 778 Docket No. 70 824 Date Sept.
1989 Amendment No.
5 Revision No.
12 Page 11-21 Babcock &Wilcox a McDermott company
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FIGURE 11-1 i
NAVAL NUCLEAR FUEL O! VISION r
R. E. TETRAULT VICE PRESIDENT l
SAFETY & SAFEGUARDS L. K. TRENT MANAGER t
i
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SAFETY SAFETY SAFETY & LICENSING REVIEW
.i T. D. LEE COMMITTEE R. L. BENNETT MMER MMER 1
i i
HEALTH LICENSING NUCLEAR HEALTH ACCOUNTABILITY SAFETY PHYSICS
-SPECIAllST l
SAFETY COMPLIANCE OFFICER SUPERVISOR i
OFFICER K. D. LONG
[
D. C. WARD F. M. Alt 0RN S. W. SCHILTHELM MANAGER C. C, BOYD
.-l __
I t
I~ INDUSTRIAL AREA HEALTH PHYSICISTSl SAFETY SUPERVISORS I
0FFICER HEALTH FHYSICS A. J. AMBROSE Sept., 1989 Lloones No SNM 778 Docket No. 70 824 Date t
5 12 11-22
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i FIGURE 11-2 1
I I
"Ti" Facilities Work Order Form Ta PLANT ENGNEDWG Dets Fr0,rr Sector
$%n.4 secuan ur cew o.i. ww ow,. na o.w,3
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DESOtPTION OF WORK TO et DCDE l
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sxpaTue ne/mmn wint saf.tr o*fw.
1 Poalth Phy' int *
(.lchnaing 8t Cornp' nno) Of ficer:,,,,_ _,,. __
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Amendment No.
Revision No.
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Babcock &Wilcox
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o 12.0 RADIATION PROTECTION 12.1 PROGRAM The radiation protection program at the site is implemented to protect employees and the general public from the haruful effects of radi-ation and radioactive material, to comply with NRC regulations, and to maintain personnel exposures as far below the limits established by the NRC as is reasonably achievable.
Implementation of the program requires the active participation of all personnel who work with licensed material or in areas were licensed material is handled.
To support the worker, the site has established the Health Physics organization and vested it with the authority and l
resources necessary to meet the program goals.
12.2 POSTING AND LABELING Many areas in the site are required to be posted to indicate the hazard present. This posting is required by the federal regulations and is a fundamental part of an effective radiaticri protection program.
Posting of areas makes the workers aware of the potential hazards in the area and assists workers in keeping their exposures ALARA. Permanent postings are the responsibility of the Health Physics l
Group. Temporary postings are the responsibility of Authorized Users.
This section discusses the posted areas at the site.
Persons not directly familiar with conditt0ns exitting in a posted area shall contact the area supervisor prior to entering and shall enter only under his direction.
12.2.1 Radioactive Materials Aree Any aru whece radleactive mett' rials are stored, h&dled, or processed in amount $ r<ceedtog 10 times the quantities specified in 10 CFR 20, Apendix C is designatea a radioettive materials area. Each area is clearly erked at every normal e.ntry with a siga bat..-ing the radiation caution symbol and kAD10 ACTIVE MATERIAL (S). Monitoring the words
- CAUTION eouipment and protective clothing required for use in the area will be specifled by tne Healtn Physics Group.
l 12.2.2 Centraination Area - This is any area in i.titch loose contamination is present in quantities in excess of those specified in Table 12-24 or an area designated by the Health Physics Group as one in l
Sept., 1989 License No SNM 778 Docket No. 70824 Date I2 12-1 Amendment No.
Reviolon No.
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i which there is a risk of contamination. Each contamination area is I
clearly marked at every nomal entry. Work in these areas may c
require a Radiation Work Pemit. Protective clothing, respiratory i
protection, and personnel monitoring devices required for entry j
into these areas must be specified by the Health Physics Group.
l Entry into the area without the prescribed equipment is prohibited,
~
When exiting a contamination area, workers must remove the protec-tive clothing and monitor himself in accordance with established i
procedures, j
12.2.3 Radiation Area - A Radiation Area is an area in which an individual could receive a radiation exposure to a major portion of the body greater than 5 mrem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or 100 mrem in 5 consecutive days.
Each radiation area is clearly marked at every nomal entry with a sign bearing the radiation caution. symbol and the words - CAUTION
+
- RADIATION AREA. Work in these areas may require a Radiation Work Pemit. Personnel monitoring devices and protective clothing to be worn in the area will be specified by the Health Physics Group.
l 12.2.4 High Radiation Area - Any area in which an individual may receive an exposure to a major portion of the body greater than 100 mRen in I hour is a High Radiation Area. High radiation areas are desig-noted by a sign at each nomal entrance bearing the radiation caution symbol and the words - CAUTION - HIGH RADIATION AREA, Entry into high radiation areas is limited to qualified persons, or under the direct supervision of a qualified person and, working under an approved radiation work permit. Protective clothing, protective equipment, and personnel monitoring devices apprnpriate for the area will be specified by the Health Physics Group and must l
be worn. When protective clothing is required, each person must i
remove the protective clothing and monitor himself in accordance with established procedures, when exiting the area.
12.2,5 Airborne Radioactivity Area - This is an area in which cirborne radioactivity concentrations could e:teeed the maximum pemissible concentration limits given in 10 CFR 20, Appendix B or in which the concentration of airborne radioactivity averaged over the nisaber of t
hours individuals ar6 in the area could exceed 25% of the limits given in 10 CFR 20. Appendix B.
Each area is clearly designated by 3
a sign at each r.omal entrance oearing the radiation caution symbol and the w rds CAUTION - AIRBORNE RADIDACTIVITY AREA. Entry is
~
lhited to those qualified persons classified as radiation workers, working under an approved radiation work permit. No entry is permitted until an appropriate area survey has been made and a memt.er of the Health Physics Group is present. Protective clothing, l
Sept., 1989 uo. nee No SNM 778 Docket No.70-824 Date 5
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protective equipment, and personnel monitoring devices to be worn in the area will be specified by the Health Physics Group and must l
be worn. When exiting these areas, each person must remove the i
protective clothing and monitor himself in accordance with established procedures.
12.3 EXTERNAL RADIATION - PERSONNEL MONITORING 12.3.1 Administrative Exposure Control - Limits for external radiation exposure are set forth in 10 CFR 20.101 and these general limits are used at the site. The applicable exposure limits to be used for operations at the site are:
1.
Whole body - 300 mrem / week (with long-tenn exposure controlled within the 1.25 Rem / quarter limit by the worker's imediate supervisor) i 2.
Skin of the whole body - 1.5 Rem / week 3.
Hands and forearms, feet and ankles - 3.0 Rem / week.
The Manager, Safety and Licensing has the authority to approve whole body exposures up to, but not exceeding, 3.0 Rem / calendar quarter.
In emergencies, the Emergency Officer is authorized to allow perconnel exposures to the whole body of up to 3.0 1
Rem / calendar quarter. Higher exposures may be authorized by the Emergency Officer in accordance with the Radiological Contingency Pl an.
i 12.3.2 Personnel Manitoring for Site and Non-site Workers - All site and non-site workers will be issued a film badge, a SRD, and a TLD.
This dosimetry will be worn by the workers when they are in che restricted area. k'har the workers letves the restricted area they will place their dociactrj on a rack previded for this purpose.
12.3J Visitor Monitoring and Escort Requirerhents - Visitors to the re-stricted area will be issued a TLD.
This dosimetry will be worn by the visitor when they are in the restricted area and will be sur-
)
rendered to thr.< receptinrict when they depart the Atte. Visitors must be escorted by a site worker when in the restricted area.
l 12.3.4 Monitoring Devices The primary device used for monitoring exposure on site is the film Sept, 1989 Lloonee No SNM 778 Docket No.70-824 Date 5
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badge. The exposure measured by this badge (reported in units of dose equivalent) becomes a part of the workers pemanent exposure i
record. Films are changed monthly and are mailed off-site for evaluation.
In some cases, a Hocith Physicist may choose to base
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the monthly exposure of an employee on the monthly thenno-l 1minescent dosimeter (TLD). This detemination shall be recorded in the employees exposure record.
l In general, the worker should wear the dosimeters on the portion of the whole body expected to receive the highest dose (with the exception of extremity dosimetry issued in special cases). The film badge and/or monthly TLD badge should always be worn in the proper orientation to ensure that exposure to non-penetrating radi-ation (e.g., beta radiation) is recorded. For cases in which the exposure may vary significantly within a small area, several badges may be worn to ensure that the maximm whole body dose is nosured.
In this context, whole body includes the head, lens of the eyes.
l the gonads, the upper legs above the knees, and the upper ams above the elbows.
12.3.4.1 Pocket Dosireters - These dosimeters are small, air-filled ionization chambers used to provide a check of the daily exposure of workers and to ensure that the administrative limit for weekly exposure is not exceeded. Indirect dosimeters are capable of measuring external exposure to gamma radiation in the range 0 to 200 mR (other ranges are also available). These dosimeters are read, recorded, and rezeroed daily. Daily readings are used also as an indication of the need to evaluate the primary dosimeter before the nomal exchange period.
Some workers may be issued self-reading pockst dosimeters (SRD).
I These dosimeters do not require reading and recharging on a daily frequency cnd the worker may evaluate his accmulated exposure without the need for a special reading device. Workers are en-couraged to read their self-reading dosimeters at least on a datly basis. These dosimeters are capable of measuring external I
exposure to genaa radiation in the range 0 to 200 mR, but other ranges are available.
12.3.4.2 Film Dadges - These dosimeters are the primary monf toring device used on site, i.e., the film badge results c.re entered in the employee's pennanent exposure record. Film badges monitor external exposure to beta and gamma radiation typically in the range IS mRems to 500 Rems. For situations in which neutron exposure is probable, film packets sensitive to neutrons also are used.
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Lloones No SNM 778 Dock.t No. 70424 Date 5
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L Films in use on site are changed monthly and mailed to an off-site dosimetry service for processing (reading, recording, and reporting).
12.3.4.3 Thermoluminescent Dosimeters (TLD) - TLD's are small, solid-state dosimeters capable of measuring external exposure from beta and gamma radiation in the range 10 mRems to 10,000 Rem. The monthly TLD's are used to duplicate the readings of the film badge.
These badges are also changed monthly and mailed off-site for processing.
At the discretion of a Health Physicist persons handling radio-l active materials may be issued extremity dosimeters.
These dosimeters are small TLD chips attached to a ring and are to be worn on the fingers. TLD " finger rings" are capable of measuring external exposure to beta and gamma radiation in the range 10 mRems to 10,000 Rems.
These dosimeters are evaluated on a frequency established by the Health Physics Group.
l 12.4 DIRECT RADIATION SURVEYS Surveys of the direct radiation exposure in areas on site are to be perfonned on a frequency established by the Health Physics Group.
In l
general, these surveys require the selection of the appropriate portable survey instruments based upon the anticipated radiation levels, the types of radiation expected, and the nature or type of survey to be performed.
Survey maps of the areas to be~ surveyed may be used to record the measured ambient radiation levels and/or, in some cases, to designate specific areas in which the exposure rates should be measured. Tne survey sbauld also include a visual exami-nation of the area for any unusual conditions or work habits which could affect the exposures received by personnel w>rking in these creas.
Items of this nature should be reported ininediately to a Health Physicist or corrected immediately, if practical.
l Results of these surveys should be reviewed by a Pealth Physicist to l
onsure that the proper posting requirements are in effect for the area ar;d to ensure that appropriate actions acc taken to keep all exposures ALARA.
Sept., 1989 Lloonso No SNM 778 Docket No. 70824 Dets 5
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l 12.5 REPORTS AND RECORDS The following records will be maintained by the Health Physics Group l
for the periods indicated.
l Health Physics Supervisor audits 2 years l
Shipping and receiving RM forms 5 years Waste disposal records
(*)
t Personnel dosimetry records Results of Bioassays and Whole Body Counting l
Releases to the environment i
Radiation survey data 2 years Contamination survey data 2 years i
Radiation Work Permits (completed) 5 years Radiation detection instrument calibration 2 years
?
Leak tests of sealed sources 2 years
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Worker training
(*)
Worker retraining
(*
l Airborne radioactivity sampling data NRC-4 forms NRC-5 forms
- - indicates that the record will be retained until the NRC authorizes its disposition.
12.6 INSTRUMENTS 12.6.1 Types - The commitment of site management to an effective radiation i
protection program includt:s the obligation to provide the adequate oquipment and supplies for such a program.
It is the responsi-L bility of the Manager, Safety and L.icensing and the Superviser of 1
Health Physics to ensure the appropriate radiation protection l
l instrumentation is availaole for use on site.
In addition, the l
Health hiysics Group has the responsibility to ensure that this l
l l
instrumentatioit is used properly, and is calibrated, maintained, L
and repaired as necessary. Minimum instrumentation requirements l
for maintaining an effective radiation protection program are
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l listed in Tables 12-1 and 12-2. Other specialized instrumentation l
may not be included in this list.
However, the exclusion of these I
instruments does not imply that their availability does not enhance the effectiveness of the radiation protection program.
l ept. N Usene.No SNM 778 Docket No. 70 824 Date 5
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l Stack particulate Alpha, Beta Bkgd. to
<1 mg/sq. cm.
.i monitor-1,000,000 cpm Stack gas Beta, gamma Bkgd. to 30 mg/sq. cm.
monitor 100,000 cpm 12.6.2 Calibration - Portable survey instruments shall be calibrated twice annually using approved procedures and sources traceable to the i
National Institute of Standards and Technology (NIST).
In addition.
l frequent operational checks will be performed on survey instraents while in use. For example, Geiger-Mueller survey instruments always indicate the presence of radiation above the ambient background.
This provides an indication that the instrument is functioning.
Portable alp'ia survey instruments are equipped with check sources which can be used to ensure that the instruments are operating correctly. Portable ionization chamber survey instruments are not equipped with an internal check source and the user must make sure these instruents are functioning before making a radiation survey.
Fixed and stationary radiation monitoring equipment is calibrated on either a semi-annual or annual basis depending on the applicable manufacturer's recomendations and established health physics
~
procedures. Operational checks are performed routinely by the Health Physics technicians on the laboratory counting equipment and
" friskers" located at exits from selected areas on site.
12.7 PROTECTIVE CLOTHING i'
12.7.1 Clothing - The following is a list of protective clothing that is available for use by personnel during nomal and maintenance condi-tions:
1.
Laboratory coats 2.
Coveralls 3.
Shoe covers, treated fabric (reusable) 4.
Shoe covers, plastic 5.
Pants, plastic 6.
Coats, plastic 7.
Hoods, fabric (reusable) 8.
Shields, spatter 9.
Glasses, plastic 10.
Glasses, glass 11.
Gloves, plastic Sept., 1989 Uoense No SNM 778 Docket No. 70424 Dets 5
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Gloves, surgeons
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13.
Gloves, heat resistant
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14.
Coats, heat reflective 15.
Hard-hats, i
.i 12.7.2 Emergency Clothing - In the event of an accident that requires special clothing or personnel protective equipment, the Fire and i
Rescue Team is provided with the following:
1.
Hard-hats, heat resistant with face shields 2.
Coats, flame resistant 3.
Boots, high top rubber with steel toe shields 4.
Gloves, chemini resistant 12.8 ADMINISTRATIVE CONTROL LEVELS _
12.8.1 Internal Occupational Exposure 12.8.1.1 Plutonium bioassay action criteria.
TABLE 12-3 PLUT0NIUM B10 ASSAY ACTION CRITERIA Bioassay Technique Action Level Action To Be Taken Urinalysis
< 0.2 dpm/L-None I
> 0.2 dpm/L 1.
Resample the individual l
within 5 working days.
2.
The Supervisor, Health Physics shall consider l
the need for wurker restriction to prevent further exposure until the diagnostic evalu-ation is complete. Only the Supervisor, Health Physics may lift any l
work restriction once it is. imposed.
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3.
If #1 is positive, in-
'l vestigate the cause and correct.
4.
If the exposure is con.
firmed by #1, investi-i gate to determine how exposure was incurred and correct it.
If the exposure exceeds 50% of-the maximum permissible annual dose, the worker i
shall be restricted from further exposure until j
' the Supervisor, Health Physics authorizes the l-lif ting of their restriction.
j 2
TABLE 12-4
)
PLUT0NIUM B10 ASSAY ACTION CRITERIA Bioassay 1
Technique Action Level Action To Be Taken In-vivo
< 1.6E-S Ci None Pu-239
> 1.6E-8 C1 1.
Restrict worker from Fu-239 further exposure.
2.
Re3 ample the individual within 10 working days.
i 3.
Determine if area surveys support the analysis results, i'
4.
If area surveys confirm result, investigate the l
Sept., 1989
'i License No SNM 778 Docket No. 70424 Date I
5 12 12-10 Amendment No.
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4 cause and take correc-I tive actions.
JL' 5.
If-the resample results do not confirm the exposure, the Super-A visor, Health Physics.
l-l may lift the work 4
restrictions.
6.
-If resample results con-firm the exposure,- the i
Supervisor, Health Physics shall determine l
the organ dose.
7.
If the exposure has exceeded 50% of the 1
maximum permissible annual dose, the worker shall remain on.a work restriction until the Supervisor, Health Physics authorizes-the -
l removal of the re-striction.
12.8.1.2 Uranium bioassay action criteria.
TABLE 12-5 URANIUM BI0 ASSAY ACTION CRITERIA
. Bioassay Technique Action Level Action To Be Taken
.a. Urinalysis
< 9 ug/L None
- b. Urinalysis 9-16 ug/L
- 1. Determine if area surveys support the analysis re-sults.
Sept,, 1989-License No SNM 778 Dock.t No. 70 824 Date 5
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- 2. If #1 is positive, in. -
l vestigate and correct as
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v needed.
- 3. Make sure individual is in-vivo counted during
~ he next time that the t
counting service is at the B&W site.
- c. Urinalysis
> 16 ug/L
- 1. Restrict the worker from further exposure.
Resemple the individual within 5 working days.-
- 2. Detemine if. area surveys -
support the analysis results.
~
- 3. If #2 is positive, in-
-vestigate the cause and correct as needed.
- 4. If exposure is confirmed 1
by #2, investigate to determine how exposure i
was incurred-and correct it.
If the exposure ex-ceeds 50% of the maximum p
permissible annual dose, the worker shall be re-
-ted from further
?
,,osure-until the Super-visor, Health Physics l
j authorizes the lif ting of l
this restriction.
- d. In-vivo
< 30 ug
- 1. None U-235
- e. In-vivo 30-120 ug
- 1. Determine if arca surveys support the analysis re-sults.
1:
i Sept., 1989 License No SNM 778 Docket No. 704?4 Data 5
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- 2. If #1 is positive, in-vestigate and correct as needed.
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'f. In-vivo
> 120 ug
- 1. Resample the individual U-235 within 10 working days.
- 2. Determine if area surveys
-l support the analysis re-i sults.
- 3. If #2 is positive, in-
.6 vestigate the cause and correct as needed.
- 4. If exposure is_ confirmed' by #1, investigate to de--
termine how exposure was incurred and correct it.
t If the exposure exceeds 120 ug, the. worker shall be restricted from-L further exposure until L
the Supervisor, Health -
i Physics _ authorizes the
_l lifting of this restric-i tion.
1 l
12.8.1.3 Beta-gamma activity - Workers who work in areas where beta-gamma I
L internal exposure is likely (Hot Cells, Radiochemistry, Health Physics) shall be in-vivo counted at approximately annual-L.
intervals.
l TABLE 12-6 FISSION PRODUCT ACTION CRITERIA I-l Analysis Action Level Action to be Taken In-vivo
>10% MPCB Remeasure subject to determine j
effective half life of the contami-nant_and plot decay curves.
l t
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Followup program will continue j
I until the contamination present-is
<5% MP0B or the effective half life has been detemined.
i Estimation
>10% MP0B Submit in vitro sample for analysis-from nasal within 5 working days.
smears or air sample i
In-vitro
>5% MP0B Resample excreta to confirm
?
presence of contamination and to establish rate of elimination.
Perform isotopic analysis if >10%
MPOB is a possibility..
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In-vitro
>10% MP0B In vivo measurement to be made as soon as practicable.
The Supervisor, Health Physics shall be responsible for evalu-l l
ations to determine the location and amount of deposition; to y
provide data necessary for estimating internal dose rates, retention functions, and dose commitments; and to detemine -
whether work restrictions or referrals for therapeutic treatment are required for any case where a result indicating a greater
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than 10% MP0B deposition of a radionuclide is verified.
~12.8.2 External Occupational Exposure - Personnel monitors (film. badges, l
dosimeters,- or other suitable devices) are provided to measure the
. radiation exposure of visitors and workers. Personnel dosimeters I
L issued pursuant to 10 CFR 20.202 shall be read on a monthly basis.
The Area Supervisors are -responsible for keeping exposures below 1-300 millirem per week and 1250 millirem per quarter.
The Super-visor, Health Physics may approve' weekly exposures above 300 I
millirem, but the quarterly limit of 1250 millirem shall not be exceeded without the approval of the Manager, SS.
If a worker has received the quarterly limit-and the Manager, SS has not authorized l
exceeding the limit, the worker shall be restricted to prevent further exposure for the remainder of the quarter.
l-l 12.8.3 Airborne Activity l:
12.8.3.1 Air Monitoring Program - Air monitoring in operating areas of the Sept., 1989 I
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1 site is accomplished with continuous monitors in predetermined.
-fixed locations. A monitor is placed.in each radioactive materials-handling area in~which there is a potential for the release of airborne radioactivity. Locations are selected based upon the ability of. the monitor to provide a reasonable evalu-ation of the. airborne activity in a particular area and to provide adequate warnings to those in the area of changing condi-tions. The deteminations are made by the Health physics Group l
based upon the operations in the area, the ptential for release, the quantity and chemical form of the material.
Alarms are set in-accordence with a particular operation, the material being. handled, and the_ potential for release. Actual alarm points are set as low as possible commensurate with the ambient radiation levels in the area.
Personnel are instructed
.through procedures and training to evacuate, up wind, if an air monitor alarms and to_ notify the Health Physics Group. Re-entry
-1s~ controlled by the Health Physics Group.
l-12.8.3.2 Effluent Monitors - Potentially contaminated air from chemical 1
l hoods,- hot cells, and glove boxes is discharged ultimately through the 50-meter stack.
Generally, e.xhaust air containing beta-gamma activity is passed through a single-stage HEPA filter p
which is sufficient to remove airborne particulates. Air from j
H more hazardous operations, e.g., from glove boxes,.is passed through a two-stage HEPA filter.
_.y Discharges through the stack are monitored with a sampling head l
l' located in the: stack about 25 feet above the base. Air removed i
i by the sampler ~ passes.through a fixed filter, into the chamber of the gas monitor, and is returned to the stack.. The fixed filter is monitored continuously for alpha and beta activity by a gas-flow proportional counter. _The second monitor, the gas monitor operates continuously utilizing a halogen-quenched GM tube. The stack monitor flow rate is maintained at a minimum of 2 cfm.
Both monitors are equipped with adjustable alarms. The set l
points for these alarms are determined by the Health Physics l
Group. The alanns are connected to an alarm panel located in the Health Physics Area in Building B.
Alanns of the system are responded to by the Health Physics Group. The alarm condition is first verified by the Health Physics Group.
If the alarm is i
actual, the exhaust fan is secured, operations' personnel are advised to stop all operations with radioactive material, the
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l cause is investigated by the Health Physics Group, corrected by operations personnel, and the fan restarted.
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TABLE 12-7 t
STACK RELEASE ACTION LEVELS l
f F.elease Product Action Level _ss Beta Particulate 200 uCi/ week Alpha Particulate 1 uC1/2 weeks (longlived)
Kr-85 70 Ci/ week i
H-3 3 C1/ week I-131 200 uC1/ week 12.8.4' Liquid Activity - Liquids containing radioactive material are' dis-l charged from the area where they are generated, to the Liquid Waste Dis)osal Facility. This facility.is comprised of a series of.
tancs. All radioactive liquid waste is held in.this facility for sampling prior to release.
If the concentration of radioactivity
. exceeds.25% of the MPC values listed in Table I, Col. 2, of 10 CFR 20, Appendix B, the waste must be diluted to levels that meet this specification.
Liquid waste is discharged to the liquid waste
' processing system at the NNFD. The NNFD rr.ust be notified and approve of each discharge from the site prior to discharge.
No alarms are associated with this system because its operation is under the positive control of the Health Physics Group.
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12.6.5 Surface Contamination 12.8.5.1 Work Areas - The Health Physics Group performs smear surveys in l
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j the work areas listed in Table 12-8.
The frequencies specified in' Table 12-8 are minimum frequencies. ' More frequent surveys 'are la performed based on the level of work performed in the specified areas. Action is taken to protect. personnel and reduce the levels of contamination below those specified. The Health Physics Group will supervise and direct the protection and l
L decontamination activities. Decontamination to reduce levels of contamination will commence within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of discovery. The Supervisor, Health Physics shall evaluate and approve any delays l
on decontamination work that are longer than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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TABLE 12-9 ACTION LEVELS FOR LARGE AREA SMEARS j
1.
Routine large Area Smears (1000-5000 dpm) - Repeat the large_
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area smear.
If results show levels of contamination above 1000 dpn, take smears in smaller arets to locate the source.
Decontaminate all areas in which the smear results indicate contamination above-1000 dpm/100 square feet.
2.
Routine Large Area Smears (5000-10,000 dpm) - Repeat the-large area smear.. If results _ show levels of contamination above 5000 dpm, isolate the contaminated area. Take smears in smaller areas to locate the source. Decontaminate all-areas in which the smear results show contamination in excess -
of 1000 dpn/100 square feet.
3.
Routine Large Area Smears (>10,000 dpm) - Isolate the con-taminated area. Survey all personnel in the contaminated area.
Take smaller smears in'the area to locate the source.
Decontaminate all areas in which the smear results show con-l tamination in excess of 1000 dpm/100 square feet. Survey all persons leaving the building.
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12.8.5.2 Personnel Contamination Surveys - Personnel are required to j
l' monitor thmnselves for activity present on their hands, shoes, j
l clothing and person before exiting a contamination area. Con-tamination monitors (friskers) are located at all normal exits from contamination areas for this purpose. The detector should be held as close to the surface of the item being monitored as possible, without touching the item, and the probe should be e
moved at a slow speed over the surface. Allowable levels of L
contamination or, skin surfaces and on' items of clothing are given I
in Tables 12-10. Any contamination in excess of these limits should. be reported immediately to the Health Physics Group. The Health Physics Group will supervise the decontamination and determine if clothing must be discarded. The approval of. the i
Supervisor, Health Physics shall be. required to allow any l
l individual to leave a contaminated area who is contaminated above background radiation levels.
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TABLE 12-10 MAXIMUM PERMISSIBLE CONTAMINATION FOR PROTECTIVE CLOTHING 2
(dpm/100 sq. cm )
Item Al pha Beta + Gamma Clothing 2,200 22,000 Shoes 22,000 220,000 12.8.5.3 Release of Equipment or Packages - Packages and equipment are surveyed by the Health Physics Group.
The Health Physics Group l
has the authority to prohibit the release of items that are found to exceed the limits specified in Annex C to License SNM-778
" Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use of Termination of Licenses for.
Byproduct, Source, or Special Nuclear Material, dated July,1982."
.12.9 RESPIRATORY PROTECTION.
The primary objective of a respiratory protection program is to limit the inhalation of airborne radioactive materials and.other hazardous materials. ' ThisL objective is normally accomplished through the use 3
of engineering controls, including process, containment, and venti-
.lation equipment. When engineering controls are not feasible or cannot_ be applied, respiratory protection must be used. The Health Physics Group is responsible for the implementation ofJ the respiratory l
protection program. The program is based on the guidance contained i
g in.10 CFR 20, Regulatory Guide 8.15, " Acceptable Programs for Respi-L ratory Protection,"Eand NUREG-0041, " Manual of' Respiratory Protection Against Airborne Radicactive Materials."
The respiratory protection program will include the following:
1-L 1.
Air sampling and other surveys sufficient to identify the hazard,-
to evaluate individual exposures, and to permit proper selection of respiratory protection equipment.
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-support equipment, and-any other operations where Health Physics believes that there-is-a potential of airborne-l activity.
'5.
It should to be noted that a major operation 1s occurring in the deconnissioning of Building C that is requiring the use of respiratory protection for-industrial-safety reasons, not for protection from radioactive materials. A number of operations are very dusty (paint chipping, concrete. destruction,etc.). A NIOSH approved full flow hard hat system is used. With no protection factor, no one in Building C has been exposed in excess of 2 MPC hr in one week.
In most cases, radioactivity above back-ground is undetectable.
12.10.2.2.3 Table 12-17 presents a summary of the air sampling program for calendar year 1984, for fixed air samplers.
TABLE 12-17 1984 AIR ACTIVITY L
H (VALUES IN pC1/ml) i l
Approximate Maximum Labs Average Concentration MPC 15*
- 1. 6E -14 1E-10 j
16*
2.4E-14 7.5E-15 1E -10 l
Soil Processing ***
1E-15 7.4E-15 4E-11 l-l H-Cask Handling Area SE-13 1.2E-11 9E-9 SE-15 SE-13 4E-11 j
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w Ip This method has been-changed such that the workers, Area Super-visors and signators.of the RWP gather'at a meeting where the proposed work scope and methods are discussed in detail. All L
facets of work are agreed to before any authorization signatures E
are placed on the RWP.
This new approval process requires more time being spent for the planning stage of a task but considerable exposure savings have resulted.
12.12 B10 ASSAY PROGRAM Those workers routinely working in contamination or airborne radio-activity areas will be scheduled for participation in the bioassay program. The Health Physics Group will select those workers to be l
sampled in the program.
This selection will be based on the probability of exposure, the worker's work habits, the type of work in the area,-air sample data, previous bioassay data, etc. Routine bioassay noy consist of check or whole-body counting (in-vivo bioassay) or. excretion analysis (in-vitro bioassay).
In-vivo bioassay is pecformed routinely by a bioassay service which comes on-site for the evaluations.
In-vitro bioassay is performed by a commercial laboratory located off-site.
Bioassay action criteria for. plutonium are outlined in Table 12-3 &
12-4.
In generol, no action is required if the excretion result (i.e., urinalysis) is less than 0.2 dpm/ liter or-the in-vivo measurement of material in-the lung is less than 16 nanocuries. All compounds of plutonium are considered to be either class W or Y.
This classification refers to the most recent evaluation of the ICRP for internal dose calculations. Class W compounds are moderately l'
soluble and clear from the pulmonary region of the lung with half-times in the range 10 to 100 days.
Class Y compounds are essentially insoluble and are considered to clear from the pulmonary region with half times of >100 days.
No compounds of plutonits are considered by the ICRP to be readily soluble (i.e.,. lass D 1
compounds which clear frcm the lungs in <10 days).
The bioassay program for uranium generally follows that outlined in Regulatory cuide.8.11. " Application of Bioassay For Uran ium," June -
1974. There are two exceptions to this general guidance:
1.
Workers off-site during the regular visit of the bioassay service will not be scheduled for a special, make-up count, if the count was scheduled only for routine exposure control monT-toring.
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p-2.- Bioassays of workers working in areas in which both plutonium
- and uranium may be airborne shall be evaluated for both plutonium and uranium.
The Supervisor. Health Physics may l
decide to analyze for only one of these elements, if it can be demonstrated that the analysis for a single element is a more sensitive indicator of an uptake.
Bioassay action criteria for uranium are outlined in Table 12-5 8 12-6.
Workers working primarily with beta and gamma emitting radionuclides will also be included in the in-vivo bioassay analysis program. Any' l
worker suspected of: an exposure greater than 40 MPC-hours will be scheduled for a bioassay evaluation as soon as practicable after the exposure. Bioassay action criteria for beta-gamma are outlined in E
Table 12-7.
t 12.13 AIR SAMPLING AND MONITORING The presence of airborne radioactive materials in the working areas
-is determined through the combined use of air samplers and monitors.
These programs are discussed below:
12.13.1 Air Sampling Program The air sampling program can be divided into two categories; fixed and portable.
Selection of the sampling category and-the
. frequency of sampling is left to the discretion of the Supervisor.
Health Physics.
l 12.13.1.1 Fixed Air Samplers - Air samples are obtained at designated points through the use of.a central vacuum system. Sampling points are located as close as possible to a permanent oF Jor station-to pennit continuous sampling of the air near the worker's breathing zone. These samples are usually ce'-
weekly.
However, the frequency may vary as the situr-dictates.
Normally, these are evaluated within two weeks, aftet v,, aing the appropriate decay period for the radon daughter products.
However, based on the particular operation, etc., a Health l.
Physicist may detennine that it is necessary to evaluate the l
samples without allowing for the decay period.
In these cases, an applicable radon decay correction factor must be applied to E
p the results.
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-12.13.1.2. Portable Samplers - Air samples in the approximate breathing zone of a worker may be obtained through the use of a lapel
-6 sampler. The-lapel sampler consists of a small sampling head attached to the worker's lapel (or collar) connected through a-small flexible tube to a small air-pump worn at the waist. The flow rates through these samplers are quite low when-compared to the fixed system. However, since the sampler is located near the nose and mouth and moves with the worker as he moves about the area, it provides a reasonable estimate of the concentration of ~ airborne radioactivity in the breathing zone of the worker.
t Air samples obtained with these samplers are evaluated on a low f
background, proportional counting system. Factors are applied to the counting results to account for background activity and detector efficiency. All results are reported in units of activity / unit volune of air sampled.
12.13.2 Air Monitoring Program
. Air monitoring in operating areas is accomplished with continuous monitors in predetennined, fixed locations.
Nontally, a monitor-1s placed in each radioactive materials handling area in which there is.a potential for the release of airborne radioactivity.
Locations are selected based upon.the ability of the monitor to provide a reasonable evaluation of the airborne activity in a particular area and to provide adequate warnings to those in the area'of changing conditions.
These determinations are made by the Health Physics Group based upon the operations in the area, the l
potential for release, and the quantity and chemical form of the material.
e Alarms are set in accordance with the particular operation, the material being handled, and the potential for release.. Actual alarm points are set as low as possible commensurate with the ambient radiation levels in the area.
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12.14'. SURFACE CONTAMINATION
- 12.14.1 ~ Smear Surveying Smear-surveys are-performed in all areas specified in the license and which, in-the judgment of the Supervisor, Health Physics, have l.
a potential for surface contamination; The frequency of these surveys will be based upon the potential-for contamination in the area, previous experience with contamination in the area, and the
.need to keep the area free from contamination.
Typical areas and survey schedules are listed in Table 12-8, however, both the areas included and the frequencies of surveys are' subject to change based ~upon the current research activities. The frequency of.
smear surveys in areas not included in ths table are generally specified in the procedure covering the particular area.
12.14.1.1-Smear Samples - Smear samples are obtained with small, absorbent filter papers.. The smear paper is moved across an area of approximately 100 sq. cm. using about 5 pounds of pressure. The smear may be< counted with a portable gas-flow proportional n
counter capable of detecting alpha or beta radiation. Normally, smear samples are evaluated in a stationary counter located in the Health Physics Laboratory. Appropriate conversion factors L
are applied to the net counts to express the smear results in L
units of disintegrations per minute.
L 12.14.1.2 Large Area Smears - Large area smears are obtained using the dust mop technique in areas around the site, the hot cell operations area, the change room and main hallways in Building B.
These smears are intended to indicate the general contami-nation environment in an area and may lead to a more-extensive survey, if unexpected contamination is indicated. Normally, l
.large area smears are evaluated with a hand-held, portable O
survey instrument (e.g., a gas-flow proportional counter such as L
the PAC 4G). - Actions to be taken in response to the results of large area smears are outlined in Table 12-22.
12.14.1.3 Action Levels - Included in Table 12-24 are the appropriate g
action levels to be used in designated areas. Decontamination shall be initiated in areas in which the removable surface contamination levels exceed these action levels. The Health Physics Group shall determine and direct the actions to be taken l
to protect workers working in these areas and to reduce contami-nation levels as far below those listed in Table 12-1 as 1s-possible. Normally, decantamination of an identified area shall begin within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the discovery.
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In.some cases-- for example', if the contamination'is discovered just prior to a weekend or:a regularly scheduled holiday,= the contaminated area may be marked and posted appropriately. Such a' determination shall be made by the Health Physics _ Group based
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- upon the severity and extent of the contamination and the potential for further contamination-of equipment and/or -
personnel during' the interval. Decontamination of the area shall begin on the first regular work-day after discovery.
TABLE 12-22 ACTION LEVELS FOR LARGE' AREA SMEARS v
1.
Routine Large Area Smears (1000 - 5000 dpm)
L Repeat the large area smear.
If results show levels of contamination-above 1000 dpm, take smears in smaller areas to locate the source.
Decontaminate all: areas in which the. smear results indicate.
L contamination above 1000 dpm per 100 sq. ft, 2.
Routine Large Area-Smears (5000 - 10,000 dpm)
Repeat the large area smear.
If results show levels of.
O contamination above 5000 dpm, isolate the contaminated area.
Take smears in smaller areas to locate the source.
Decontaminate all areas in which the smear results show contamination in excess of 1000 dpm per 100 sq. ft.
3.
Routine large Area Smears (>10,000 dpm) l L
Isolate the contaminated area.
Survey all personnel in the contaminated area.
Take smaller smears in the area to locate the source.
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Hot Cell Operations Area twice monthly 2,000 Cask Handling Area twice monthly 22,000 Radiochemistry Laboratory twice monthly 22,000 Exit Portals From Controlled twice monthly 2,000 Areas 12.14.2 Direct Radiation Surveys Surveys of the direct radiation exposure are to be performed on a frequency established by a Health Physicist.
In general, these l
surveys require the selection of the appropriate portable survey instrinnents based upon the anticipated radiation levels, the types of radiation expected, and the nature or type of survey to be performed.- General maps of the areas to be surveyed may be used to record the measured ambient radiation levels and/or, in some cases, to designate specific areas in which the exposure rates should,be measured. The survey. should also include a visual-examination of the area for any unusual conditions or work habits which could affect the exposures received by personnel working in these areas.. Items of this nature should be reported immediately to the Supervisor, Health Physics.or corrected immediately, if l
practical.
Results of these surveys should_ be reviewed by a Health Physicist l
to ensure that the proper posting requirements are in effect for the area and to ensure that appropriate actions are taken to keep all' exposures ALARA.
Action levels for direct radiation surveys are presented in Table 12-24.
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TABLE 12-24 I
CONTAMINATION ACTION LEVELS-Transferable Surface Type of Fixed Contamination Area Radiation Surface Reading (dpm/100 sq. cm.)
Uncontrolled' Alpha 300 dpm/100 sq. cm.
30 l
Beta-Gamma 0.1 mrad /h 220 Contamination
- Alpha 3000 dpm/100 sq. cm.
2,200
. Beta-Gamma-1.0 mrad /h**
22,000
- The Supervisor, Health Physics may raise these action levels, l-Justification for this action must be documented and forwarded to the Safety Review Committee for their review and approval.
- This action limit applies to contamination areas which are normally.
radiation areas. This level of contamination will not cause a sig-nificant increase in radiation exposure.
NOTE:
This table provides limits above which decontamination must be initiated.
These action levels pertain to areas normally accessible to personnel performing normal work functions. The levels do not a) ply to areas requiring extraordinary precautions for entry, e.g., tie Isolation Area, waste water tanks, etc.
In these cases, direct health physics coverage is
-the primary control mechanism.
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12.14.3 Personnel Contamination Surveys i-Workers are required to monitor themselves for activity present on their hands, shoes.. clothing, and person before exiting a con-tamination area. Contamination monitors-(friskers) are located at all exits from contamination areas for this purpose.
The detector (probe) should be held as close to the surface of the item being monitored'as possible (without-touching the item) and the probe should be moved at a speed of about 0.5 inch /second.. Allowable levels of contamination on skin surfaces and personal clothing.
must not exceed background. Permissible levels of contamination on protective clothing are given in Table 12-10., Any contamination in excess of these limits should be reported immediately to the Health Physics Group.
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Discharge through the stack is. accomplished with _a large blower, powered nomally by a large electric motor operated on off-site power.
Emergency power is supplied by an internal combustion engine coupled to the blower shaft through a centrifugal clutch. On loss of off-site power, the engine starts automatically and takes over the load upon reaching.the proper speed.
Discharges through the stack are monitored with a sampling head located
.in the stack about 25 feet above the base. Air removed by the sampler
. passes through a fixed filter, into the chamber of the gas monitor, and is returned to the stack.
The fixed filter is monitored continuously for alpha and beta activity by. a gas-flow proportional counter. The second monitor, the gas monitor, operates continuously utilizing a halogen-quenched GM tube. The stack monitor. flow rate is maintained at
- a minimum of 2 cfm. - Both monitors are equipped with adjustable alarms.
Set points for these alarms are determined by the Health Physics Group.
l These alarms are connected to an alarm panel located in the Health
. Physics Laboratory in Building B.
Air from-areas equipped with continuous air monitors (and which is'
. below the applicable MPC for an unrestricted area) may be exhausted, through HEPA filters, directly to the roof of the building. Air from L
areas which have a low potential for airborne activity may be exhausted directly to the roof of the building.
13.3 LIQUID EFFLUENT MONITORING ll All potentially radioactive liquids are collected in tanks located in L
the Liquid Waste Disposal Facility.
The contents of each tank are L
mixed, samples are obtained, and are analyzed-for radioactivity before 1i L
the liquids are released to the waste treatment plant at the Naval Nuclear Fuel Division (NNFD).
Liquid waste tanks are sampled on a quarterly frequency, before release to the NNFD or at other times determined by the Health Physics Group.-
l Results of all analyses are reported in units of activity per unit i
volune and records of these evaluations are retained by the Health Physics Group.
I Water samples are also obtained on a quarterly basis from the retention L
basin' located behind Building C, the sample pit and collection tank located adjacent to the Temporary Storage Facility, and the holding pond located near Building J.
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i 14.0 NUCLEAR CRITICALITY SAFETY 5
14.1 ADMINISTRATIVE AND TECHNICAL PROCEDURES The ultimate responsibility for nuclear criticality safety rests with the Manager, SS.
However, first-line responsibility is with the Licensing & Compliance Officer supported by the Nuclear Criticality Safety Officer.
t The Nuclear Criticality Safety Officer is generally responsible for establishing nuclear safety limits and nuclear safety considerations
-i in operating procedures, processes, and the like. His duties are shown more specifically in the following statement.-
The position of Nuclear Criticality Safety Officer has been estab-lished'at the site. 'It will be this officer's responsibility to ensure, as far as.possible. that no operations on site can lead to the inadvertent assembly of a critical mass.
To this end, he will l
review all new procedures which involve the handling of special nuclear materials as well as changes in old procedures, observe oper-ations, inaugurate educational programs if and when he deems them necessary, and carry out confinning criticality calculations.
This appointment does not in any way relieve the Licensing & Compli-ance_ Officer of his responsibilitier. for ensuring the safety of operations,'nor will it eliminate the necessity for the reviews by the Safety Review Connittee required by the license.
Once a quarter the Nuclear Criticality Safety Officer or qualified I
person designated by him will inspect all site operations where special nuclear materials are being processed. Other areas shall be inspected less frequently; however, all areas shall be inspected at i
least once a year
'He shall consider area operations when schedul-ing these-inspections and shall, if necessary, schedule his inspection at more frequent intervals. -His consideration should include inspection of new facilities, inspection of hazardous non-routine operations, an audit of nuclear criticality safety records, a check for area posting and a review of current practices.
A written report is to be filed with the Manager, SS quarterly with a copy to the Licensing & Compliance Officer. The report shall be brief, concerning itself with inspections made during the quarter and with the nuclear criticality safety activity of the quarter.
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1 From these data 'it is concluded that for 850 grams U-235 per unit _
an array of 24-inch centers should be safe for 40 units or less and on 36-inch centers, an array would be safe.with 90 units or-i less. A slight increase in the array multiplication, on the order of 1%, may occur for low levels of interspersed water Ll moderation.
However, the safety of. these arrays would still be maintained.
i To avoid confusion and possible mistakes, additional procedural controls are applied when low-enrichment limits are used.
These preclude enrichment combinations of below and above 4.0 wt%
(These are not necessarily unsafe - no calculations were made and no such combinations are desired.)
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4.
The' unit and its limit (laboratory,. furnace, transfer cart, l
L etc.) are established by the Licensing & Compliance Officer, l
t who authorizes posting the limit showing the maximum quantity' of plutonium, U-233, and U-235 allowed. The fissile material content of the material transferred to or from a unit is established from process records, analyses, or previous analytical data. Only authorized users of SNM may transfer
-SNM between units and must do so only according to approved procedures. A board, sign, or other acceptable device is used to record the new balance and compares to balance with 3
the unit limit.
14.3.2.3 Hot Cell - The demonstration for the units and array is identical to that of 14.3.2.1 and 14.3.2.2.
The individual hot cells are isolated from all other arrays by a minimum of 2 feet of high density concrete.
14.3.2.4 Underwater Storage - Transfer Canal - Underwater aluninum or
~
L stainless steel storage racks are constructed to ensure 12-inch i
edge-to-edge spacing of each unit. Units are limited to those in t
- 4. 2. 2. 2.1 & 4. 2. 2. 2. 2 excluding PWR fuel assemblies and, since' they_ are separated by 12 inches of water, units are considered l
isolated. Therefore, any number of these units may be used.
E l
Racks and fixtures are constructed with sufficient integrity and l
strength to withstand reasonable structural deformity, thereby L
providing the spacing previously outlined. Supervisory approval l
1s required for removing or inserting any subcritical unit'out of p
or into its storage rack.
Sept., 1989 License No SNM 778 Docket No. 70424 Date 5
12 14-8 Amendment No.
Revision No.
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