ML20215L147
| ML20215L147 | |
| Person / Time | |
|---|---|
| Site: | 07000754 |
| Issue date: | 04/06/1987 |
| From: | Cunningham G GENERAL ELECTRIC CO. |
| To: | Cunningham R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 8705120114 | |
| Download: ML20215L147 (63) | |
Text
h-RETURN T(y M;gg 78-78b PM/PzvP GENERAL $ ELECTRIC NUCLEAR ENERGY BUSINESS OPERATIONS GENERAL ELECTRIC COMPANY e VALLECTOS NUCLEAR CENTER e PLEASANTON, CAUFORNIA 94566 April 6, 1967 T
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RECEIVED e
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APR 13 ;gg7 )';
Mr. Richard E. Cunningham, Director Division of Fuel Cycle and Material Safety 9 U.S.huClEAR RECUMTORY Office of Nuclear Material Safety and Safeguards E0*rlsslog
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U. S. Nuclear Regulatory Commission g
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20555
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8
References:
- 1) License ShW-960, Docket 70-754.
- 2) "Vallecitos Nuclear Center Radiological Contingency Plan";
November, 1982.
Dear Mr. Cunningham:
Enclosed are revised pages for the radiological contingency plan for the Vallecitos Nuclear Center. The changes in the plan reflect changes in the site organization structure and reductions in some site activities. A number of the changes are only editorial. None of the revisions reduce the effectiveness of the plan.
A summary of the changes is attached.
Sincerely, L
& C.
J G. E. Cunningham Senior Licensing Engineer g,
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s GENER AL $ ELECTRIC Change Page No-E2 _
Reason for Change 1
11 Change on p. 1-21 caused page number change.
2 vii Title of " Security Shift Supervisor" changed to " Security Shift Specialist".
3 ix Name of the Irradiation Processing Operation (IPO) has been changed to Irradiation Processing (IP).
Therefore, Manager, IPO, is now Manager, IP.
4 x
The " Breach of Security" emergency procedute has been deleted from this plan as it does not apply to any areas that conduct activities pursuant to License SNM-960.
5 1-1 Possession limit for Co-60 has been increased from 1,500,000 to 2,000,000 curies.
6 1-2 "100 g of U-235" changed to "100 g of U-233" (typo).
7 1-3 Current status of GETR indicated by describing it as " shut down".
8 1-10 To better describe site water supply capability.
9 1-16 Trailers 102L and 102M deleted from east of Building 102F.
10 1-21 Shows that FFL has been deactivated.
11 1-21 Paz. 1.2.7.2.3 added to provide description of the 102 Annex.
12 1-21 Building 104 usage changed.
13 1-24 Par.1.3.'.2, description of FFL deleted.
14 1-25 See No. 12.
15 1-25 Nuclepore tape irradiations deleted.
16 1-26 Shows that instrument shop moved to Building 106.
17 1-28 Indicates that Building 400 " partially" decontaminated rather than " decontaminated to nonsmearable" condition.
j Page 1 of 5
s GENER AL $ ELECTRIC Change Page No.
L Reason for Channe 18 1-32 Updated Table l'.3-1 with the following changes:
Column Stack No.
Stack Location, Building No.
45, 46 Stack' Size 16, 17,' 21, 22, 26, 30, 37, 38, 41, 45, 46, 50 Nominal Stack Flow Rate 4, 12, 16, 26, 30, 34, 37, 45, 46, 48, 50 Sampling Flow Rate 12, 31 Type of Sampling 12, 26, 31, 37 Also showed Stack Nos. 46 and 50 as "on standby; not operated routinely".
19 2-1 Reference to CETR SAR deleted as inappropriate information.
20 2-4 This is the first place the BET is mentioned, so reference to Par. 4.2.2.6 which describes the BET was added.
j 21 2-5 Flow rates for Buildings 102 and 103 stacks changed to reflect current status.
22 2-5 "90 !! EPA filters" changed to "30 HEPA filters" (typo).
23 2-6 "40 llEPA filters" changed to "20 HEPA filters" (typo).
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24 2-10 Added " Selected" to avoid the misinterpretation that all site personnel receive fire training.
25 2-11 See No. 3.
j 26 2-13 See No. 3, 27 2-14 Makes the Area Manager responsibility assignment consistent with that in SNM-960, Appendix A; i.e.,
for " activities in criticality and radiation areas".
28 2-16 See No. 3.
29 3-1 See No. 3.
Page 2 of 5
i GENERAL $ ELECTRIC Change Page No.
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Reason for Change 30 4-1 Update of organization and position names.
31 4-2 See No. 30.
32 4-3 See No. 3.
33 4-4 NEB 0 Director, Medical Services, no longer readily available for emergency response at VNC.
The Occupational Health Nurse has been assigned his emergency preparedness and response responsibilities.
34 4-4 See No. 3.
35 4-5 See No. 3.
36 4-7 See No. 33, 37 4-8 See No. 3.
38 4-8 First sentence changed to indicate not every Area Manager appoints a BET. Remainder of paragraph changed to permit designation of BET that is capable of performing the same functions as currently required but with fewer personnel.
39 4-9
" Ensure" changed to " Assure" to indicate difference between BEC's and Area Manager's responsibilities.
40 4-11 There no longer is an organization titled, "VNC Medical Services". See No. 33, 41 4-11 Time spent by the company physician at VNC has been reduced.
I 42 4-12
" Department of Health" has been renamed " Department of Health l
Services" and the " Radiological Health Section" changed to l
" Radiologic Health Branch".
Incorporated comments from an OES engineer regarding the responsibilities of the State organizations.
43 5-6 To indicate that only one portable air sampler is available for use where 115 VAC is unavailable.
44 5-7 Discussions about TLD's deleted as this is no longer an option for emergency response.
45 5-8 The word " External" has been deleted from the title of VSS 5.2.
Page 3 of 5
i GENER AL $ ELECTRIC Change Page No.
E2 _
Reason for Chango 46 5-8 See No. 33.
47 6-2 See No. 3.
48 6-2 The currently assigned physician is not certified by the "American Board of Preventive Medicine".
49 6-2 Wording changed to delete the name " Medical Department" which is no longer the correct organizational name.
50 6-5 Descriptive information about the Eberline AHM-20 deleted as these instruments have been removed from service.
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51 6-5 CP Model 2 no longer is used. Models 4 and 5 are the currently used instruments.
52 6-7 Use of the temperature and humidity sensors at the 5-foot elevation has been discontinued.
53 6-9 The test of the criticality alarm system was previously changed from monthly to quarterly.
" Monthly" was overlooked in this paragraph.
54 7-1 The NRC requested that the biennial review cycle be returned to an annual review.
55 7-1 To indicate that fire fighting training is provided by the Site Fire Marshal rather than by Nuclear Safety.
56 7-2 To indicate that RSVNC is not required for all personnel that have unescorted, uncontrolled access to Posted Radiation Areas.
57 7-2 Deleted statements about respiratory protection training for emergency response personnel as this is addressed in the VNC Respiratory Protection Manual.
58 7-2 "Without direct supervision" was added to make this consistent with the actual criticality training requirement.
59 7-2 Information regarding a course titled " Radiation Detection Instrumentation" was deleted as this course was found to be unneeded and no longer is available.
60 7-3 Paragraph number changed.
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i GENERAL $ ELECTRIC 1 Change Page No-E2 _
Reason for Chance 61 7-3 Acronym for course changed from "EEART" to " FARED".
Course was not changed.
62 7-3 Paragraph number changed.
63 7-5 See No. 3.
64 7-5 See No. 54.
65 7-6 To indicate that currently, responsibility for SCBA maintenance is assigned to the Manager, RHO.
66 7-7 See No. 33.
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3/87 GENERAL ELECTRIC COMPANY NUCLEAR ENERGY BUSINESS OPERATIONS VALLECITOS NUCLEAR CENTER RADIOLOGICAL CONTINGENCY PLAN NOVEMBER, 1982 (REVISED MARCH, 1985)
(REVISED JUNE, 1986)
(REVISED MARCH, 1987) l i
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3/87 TABLE OF CONTENTS h!Ln INTRODUCTION............................................................. vi SYNO PS I S O F EM ERG ENCY PROC EDUR ES......................................... vii 1.0 GENERAL DESCRIPTION OF Tile PLANT / LICENSED ACTIVITY................
1-1 1.1 Licensed Activity Description................................
1-1 1.1.1 Location............................................
1-1 1.1.2 Licenses.............................................
1-1 1.1.3 Products.............................................
1-2 1.1.4 Wastes............................................... 1-2 1.2 Site and Facility Description................................ 1-3 1.2.1 Cenera1..............................
1-3 1.2.2 Site Location........................................
1-3 1.2.3 Site Description...................................
. 1-9 1.2.4 Demography..........................................
1-10 1.2.5 Commercial and Recreational Facilities...............
1-14 1.2.6 Transportation....................................... 1-14 1.2.7 De scrip tion o f VNC Facilitie s........................ 1-15 1.3 Process Description.........................................
1-23 1.3.1 Genera1............................................
1-23 1.3.2 Building 102.......................................
1-23 1.3.3 Building 103.......................................
1-24 1.3.4 Building 104..
1-25 1.3.5 Building 105.......................................
1-25 1.3.6 Building 106.......................................
1-26 1.3.7 Area 200 (CETR)....................................
1-27 1.3.8 Area 300...........................................
1-27 1.3.9 Area 400...........................................
1-28 1.3.10 Plant Nonradioactive Wastewater Systems............. 1-29 1.3.11 Radwaste Systems....................................
1-30 2.0 ENGINEERED PROVISIONS FOR APNORMAL OPERATIONS.....................
2-1 2.1 Criteria For Accommodation of Abnormal Operations............ 2-1 2.1.1 Process Systems.................
2-2 2.1.2 Alarm Systems and Release Prevention................
2-3 2.1.3 Support Systems.....................................
2-4 2.1.4 Control Operations..................................
2-11 2.2 Demonstration of Engincered Provisions for Abnormal Operation......................................
2-12 l
2.2.1 Process and Support Systems.........................
2-13 2.2.2 Alarm Systems and Release Prevention capability.....
2-13 2.2.3 Support Systems...................................... 2-13 2.2.4 Control Operations............
2-13 l
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O f.a&R 3.0 CLASSES OF RADIOLOGICAL CONTINGENCIES.............................
3-1 3.1 Classification System.......................................
3-1 3.2 Emergency Classification and VNC Actions..................... 3-2 3.2.1 Notification of Unusual Event........................ 3-2 3.2.2 Alert................................................ 3-3 3.2.3 Site Area Emergency.................................
3-4 3.3 Range of Postulated Accidents...............................
3 5 3.3.1 Action Levels - Notification of Unusual Event........ 3-5 3.3.2 Action Levels - Alert................................ 3-6 3.3.3 Action Levels - Site Area Emergency.................
3-7 4.0 ORGANIZATION FOR CONTROL OF RADIOLOGICAL CONTINGENCIES............
4-1 4.1 Normal Plant Organization...................................
4-1 4.2 On Site Radiological Contingency Response Organization......
4-3 4.2.1 Direction and Coordination..........................
4-3 4.2.2 Site Staff Radiological Contingency Assignments.....
4-6 4.3 Off-Site Assistance To Facility.............................
4-10 4.3.1 Medical Treatment Facilities........................
4-10 4.3.2 First Aid Personnel and Ambulance Services..........
4 11 4.3.3 Services of Other Medical Personnel On Site.........
4-11 4.3.4 Fire Fighting Backup................................
4-11 4.3.5 Police Assistance...................................
4-11 4.3.6 0ther...............................................
4-11 4.4 Coordination With Participating Covernment Agencies......... 4-11 4.4.1 County..............................................
4-12 4.4.2 State...............................................
4-12 4.4.3 Federal.............................................
4-13 5.0 RADIOLOGICAL CONTINGENCY MEASURES.................................
5-1 5.1 Activation of Emergency Control Organization.................
5-1 5.1.1 Emergency Communications.............................
5-1 5.1.2 Description of Available Media....................... 5-2 5.2 Assessment Actions..........................................
5 3 5.3 Corrective Actions...........................................
5-3 5.4 Protective Actions...........................................
5-4 5.4.1 Personnel Evacuation From Immediate Area............
5-4 5.4.2 Personnel Evacuation From Site and Accountability...
5-4 5.4.3 Use of Protective Equipment and Supplies............
5-5 5.4.4 Contamination Control Measures......................
5-5 111
PA&E 5.5 Exposure Control In Radiological contingencies..............
5-5 5.5.1 Emergency Exposure Control Program..................
5 6 5.5.2 Decontamination of Personne1........................
5-8 i
5.6 Medical Transportation......................................
5 8 5.7 Medical Treatment...........................................
5-11 6.0 EQUI PM ENT AND FACI LITI ES.......................................... 6 - 1 6.1 Control Point................................................
6-1 6.2 Communication Equipment.....................................
6-1 6.2.1 Telephone............................................ 6-1 6.2.2 FM Transceivers.....................................
6-1 6.2.3 All-Call System.....................................
6 2 6.2.4 High Level Conference Circuit (HICON) System........
6-2 6.3 Fac ili ty Fo r Ass e s smen t Teams............................... 6 2 6.4 On-Site Medical Facilities..................................
6 2 6.4.1 Site Medical Dispensary.............................
6-2 6.4.2 Personnel Decontamination...........................
6 3 6.5 Emergency Monitoring Equipment............................... 63 6.5.1 Pe rsonnel Survey Me te rs............................. 6 3 6.5.2 As se s sme nt Sys tems................................~..
6 7 6.5.3 Emergency Mobile Equipment........................... 68 6.5.4 Criticality Alarm Systems...........................
6 8 6.5.5 Fixed Monitoring Equipment..........................
6 8 7.0 MAINTENANCE OF RADIO 1DCICAL CONTINGENCY PREPAREDNESS CAPABILITY 71 7.1 Written Procedures..........................................
7 1 7.2 Training....................................................
7 1 7.2.1 Emergency Training Program..........................
7 1 7.3 Te s ts and D r i11 s...........................................
7 - 5 I
7.4 Review and Updating of the Plan and Procedures..............
7-5 7.5 Maintenance and Inventory of Radiological Emergency Equipment, Instrumentation and Supplies.....................
7 6 7.5.1 Maintenance Responsibility..........................
7-6 7.5.2 Calibration and Maintenance Procedures..............
7-7 7.5.3 Emergency Supplies..................................
7 8 l
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a f.A&R 8.0 RECORDS AND REP 0RTS...............................................
8 1 8.1 Records of Incidents........................................
8-1 l
8.1.1 Incident Investigation Report........................ 8-1 8.1.2 Operational and Regulatory Forms....................
8 2 8.1.3 Retention of Reports and Forms......................
8 3 8.2 Records of Preparedness Assurance...........................
8 3 8.3 Reporting Arrangements......................................
8 4 1
8.3.1 Off-Site Notification...............................
8-4 9.0 REC 0VERY..........................................................
9-1 9.1 Reentry.....................................................
9-1 9.2 Plant Restoration...........................................
9 2 j
9.3 Re s ump tio n o f Ope ra tions....................................
9 - 2 I
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Tables 1.2-1 Summary of Population out To 10 Miles........................... 1-12 1.3-1 Stack and Stack Sampler Data.................................... 1 32 5-1 Protective Action Guides (PAC) For Limiting Exposure To Radiation and Radioactive Materials Under Emergency Conditions.....................................................
5-9 6-1 Laboratory Counting Systems....................................
6-10 1
Figures 1
i 1.2-1 Vallecitos Nuclear Center (Lookin5 NE).........................
1 4 1.2 2 vallecitos Site................................................
1 5 1.2-3 Bay Area Map...................................................
1 6 1.2 4 Pleasanton Quadrangle..........................................
1 7 1.2-5 Topographical Map Vallecitos Nuclear Center..................
1-8 1,2 6 Map Showing Resident Locations Adj acent To VNC.................
1 11 i
1.2-7 Population Sectors Out To 10 Miles..............................
1-13 1,2-8 Plot Plan - 100 Area...........................................
1-16 i
1.2-9 Plot Plan - 200 Area...........................................
1-17 1
1.2 10 Plot Plan - 300 Area............................................
1-18 1.2 11 Plot Plan - 400 Area............................................
1 19 4-1 VNC Emergency Control Organization.............................
4 4 APPENDIX A List of Documents Containing Detailed Information 4
For VNC Facilities i
APPENDIX B - VNC Site Emergency Procedures v
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o INTROD"CTION The Nuclear Regulatory Commission has directed certain licensees to prepare and submit radiological contingency plans for review and approval.
For completeness, the plan must include descriptions of (1) facilities; (ii) chemical and physical processes; (iii) types, forms, and quantities of radioactive and other hazardous materials; (iv) distribution of radioactive material inventories; (v) specifications of structures, systems, and components important to safety; and (vi) the elements of emergency planning.
Radiological contingency planning is required for those licensed tacilities/ activities exhibiting the potential for accidents which could result in:
(i) off-site radiation doses execeding 1 Rem to the whole body, 5 Rems to the thyroid, or 3 Rems to other critical body organs; (ii) potentially serious radiation overexposures of workers from a nuclear criticality incident or release of radioactive materials; or (iii) chemical exposures which could impact radiological safety.
Radiation doses of 1 Rem to the whole body and 5 Rems to the thyroid are the lowest Protective Action Guides (PACS) established by the Environmental Protection Agency for triggering a protective action in l
public areas following a radiation accident.
General Electric Company (GE) has been engaged in nuclear energy work at the Vallecitos Nuclear Center since 1955. A review of GE compliance history and of the related IE Inspection Reports demonstrates the success of GE's facilities, processes, engineered safety features, and organizational and administrative procedures for safely conducting operations in the nuclear industry and for proventing and mitigating the consequences of off-normal events, including emergencies.
It is concluded that the management organization, administrative controls, facilities, equipment and process systems, service and support systems, other engineered safety features, and materials at risk are such as to limit the consequences of postulated accident events beyond the site boundary to less than the lowest Protective Action Guide values established by the EPA.
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o 3/87 SYNOPSIS OF EMERGENCY PROCEDURES The VNC Emergency Procedures Manual, " Site Emergency Procedures - VNC", is attached to this radiological contingency plans document as Appendix B and shall be utilized in the event of the declaration of any emergency at the VNC site.
The emergency manual, " Site Emergency Procedures - VNC", consists of a general emergency control procedure plus individual procedures for specific types of emergencies. Procedure A-5, " Emergency Control Procedure - General",
identifies an emergency control organization, summarizes the responsibilities of key personnel, briefly describes the emergency communication systems, and describes a classification system for emergencies. Other procedures in the emergency manual are:
l B-5, Bomb Threats C-5, Fire Protection D-5, Criticality Emergency E-5, Radiation Emergoney F-5, Confrontation C-5, Civil Disorder H-5, Earthquake, Tornado and Hurricane J-5, Major Power Outage K 5, Breach of Security L 5, External Release of Emer6ency Information Bomb Threats Site personnel receiving a bomb threat will immediately notify the Security Shift Specialist, who will immediately notify the Emergency Operations l
Coordinator (EOC) and the Specialist, Safeguards, or his designated alternate.
These persons will be responsible for decision making and initiating bomb threat response plans.
The procedure for handling bomb threats describes detailed aspects of the search patterns, squad organization, and how the alert is terminated after all areas have been cleared.
If an object of a suspicious nature or shape, the sound of a clock ticking, or other unidentifiable objects are located, the EOC is to be notified so that steps can be initiated to isolate the area and provide qualified inspectors to correct the situation. Under no condition should an object of a susoicious nature be touched or disturbed by an emoloyee.
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Fire Protection Trained personnel on site respond to all fire alarms.
Response personnel are trained in the use of plant fire extinguishers and other equipment used to fight incipient-stage fires.
If a fire or explosion should occur, the Site Emergency Control Organization, under the direction of the Emergency Operations Coordinator, will initiate immediate action to control damage. The California Division of Forestry Fire Station and other emergency organizations, as required, will provide assistance.
Criticality I
In the event of a criticality alarm which may be initiated by an inadvertent criticality or some other event that causes high radiation levels, personnel in the affected building must evacuate immediately.
They will follow evacuation signs to an Assembly Area and remain at that area until they receive further instructions.
The criticality or high radiation level event is divided into two phases.
The first, or evacuation phase, involving the evacuation of the affected area and the announcement of the possible criticality, lasts from the moment the alarm sounds until the re-entry team makes a radiation survey to determine the nature of the event.
The second phase involves the more extended period from the end of the first phase until the end of the emergency is declared.
The primary objective of the accident response will be to assure evacuation of personnel from areas of significant radiation levels, rapid determination of radiation levels, identification of personnel who may have received significant radiation exposure and their placement under medical supervision, directions to other personnel, and placement of the facility in a nonemergency condition.
Radiation Emercency This procedure is concerned with radiation emergencies which involve a release of radioactive material that endangers or threatens to endanger employees 1
outside the immediate area in which the emergency is generated or off-site persons or property. This procedure does not substitute for, but is inter-related with the other VNC individual contingency situations, in particular the Fire, Bomb, and Criticality Procedures.
The basic elements of this procedure are:
1.
plans for expedient notification of emergency personnel; 2.
identifies radiation emergency response personnel; 3.
provides for notification of local, state, and federal agencies.
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3/87 Confrontation A confrontation is considered to be a receipt of a " request for appointment" with the Company Management, or a person in authority, from a group either by letter, by telephone, or by unannounced appearance at the site; or a similar occurrence which constitutes a confrontation between outside persons and the site.
This confrontation control procedure is designed to handle a confrontation group which initially is peaceful.
Instructions in Procedure G-5, Procedure for Control of Civil Disorder, will be implemented if the situation warrants in the judgement of the Emergency Operations Coordinator.
Control of Civil Disorder This procedure covers all civil disturbances involving VNC employees, except labor disputes which are covered by a separate employee relations procedure plan. The Manager, 1P, and the Manager, Nuclear Safety, will be kept informed l
of all action taken by local authorities and site personnel.
The Emergency Control Organization will be the liaison with all government, police, and emergency agencies.
Earthouake and Hurricane In the event of a major earthquake, hurricane, flood, or tornado, the Emergency Control Organization will be activated, establish their control in Building 102B or at an alternate center which sustained the least damage, and 1
proceed according to the procedure.
The procedure provides emergency teams to secure areas as quickly as possible by:
1.
shutting off operating equipment; 2.
shutting off main gas valves, switches, etc.;
3.
fighting any fires which may have started; 4.
surveying to determine the status of radiation / radioactive material containment integrity.
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i-3/87 Ma_ior Power Outare l
The procedure for handling a major power outage outlines the course of action to be taken in the event of a major electrical power outage at the VNC site.
WhenL a major power outage has occurred.the EOC shall, Lif required, establish man Emergency Support Center. The Manager, Reactor Operations and Support Services, will be in control of the electrical repair team and is responsible
.for coordinating the activities of the contractor technical teams,uif needed.
During off-shift hours, managers and supervisors normally'having processes.
underway which would be affected. adversely by power outages will be notified by the emergency communications center in order to initiate prompt corrective action to minimize losses and damage. Available information on estimates for resumption of services also will be provided by the emergency _ communications -
center. Where appropriate, supporting procedures are developed by' Area Managers and issued to provide specific action guidelines to concerned personnel within certain laboratories and shops.
Breach of Security-l This procedure applies to areas regulated by 10CFR73. There are no such areas that conduct activities pursuant'to License SNM-960.
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l-1 3/87 1.0 GENERAL DESCRIPTION OF THE PIANT/ LICENSED ACTIVITY 1.1 Licensed Activity Description 1.1.1 Location The Vallecitos Nuclear Center (VNC) is located 4.1 air miles south-svatheast of Pleasanton, California, on the north side of State Route 84 (Vallecitos Road). The site crea is approximately 1,600 acres. The entire site is fenced, with approximately 100 acres fenced separately. All site facilities are located in the inner 100 acres.
1.1.2 Licenses Special nuclear materials are handled at VNC under License SNM-960.
Activities involving source and by-product materials are conducted under State of California License 0017-60. Activities involving SNM, source material, or by-product material at the research reactor (NTR) are conducted under License R-33.
Three deactivated reactors are maintained in a " possess-only" status under Licenses DR-10, DPR-1, and TR-1.
1.1.2.1 License SNM-960 License SNM-960 permits the possession of up to 50 kg of U-235 enriched to less than 10 percent, 4 kg of U-235 enriched to more than 10 percent, 500 g of Pu, and 200 g of U-233.
The materials may be possessed in any form, including irradiated material with its' attendant by-product material and reactor-produced transuranics.
Activities ccnducted under License SNM-960 include inspection of irradiated reactor fuels in hot cells and research and development activities involving reactor fuels.
1.1.2.2 License 0017-60 License 0017-60 issued by the State of California authorizes possession of any radionuclides except special nuclear material in various quantities and forms and for various purposes. Possession limits range from 100 curies for any radionuclide in any form to 2,000,000 curies of Cobalt-60.
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1-2 3/87 1.1.2.3 License R-33~
Activities at the General Flectric Nuclear Test Reactor (NTR) are conducted under License R-33.
The license permits possession of 4 kg of contained U-235 as in-core fuel; 100 g of Pu for use in experimental devices, instrument check sources, and as encapsulated fission foils; 700 g of contained U-235 or.1,500 g of contained U-235 in uranium enriched to less-than 4% U-235, not to be used L
as in-core fuel; 100 g of U-233 for use in experimental devices and ionization l
chambers; 9.1 kg of source waterial for experimental devices; 200 Ci of by-product material in activated solids or as contained materials; 10 Ci of H-3 for pulsed neutron sources; and such by-product material as may be
. produced by operation of the reactor.
In. addition, the types of special nuclear materials licensed under SNM-960 may be used in some NTR facilities.
The NTR is a general research and development reactor operated at a maximum power level of 100 kilowatts. As such, its uses are varied. They include but-are not limited-to neutron radiography, reactivity studies, and instrument calibrations.
1.1.3 Products The VNC is a research and development facility primarily in support of GE and' customer nuclear energy programs. However, certain by-product radioisotopes are encapsulated for commercial distribution.
1.1.4 Wastes Wastes are typical of reactor, hot cell, and laboratory operations.
They include low specific activity solid wastes (e.g., laboratory equipment, chem l
wipes), contaminated hot cell equipment, segmented fuel rods, de-watered l
resins, etc.
Low-level liquid wastes are processed at the site liquid waste j
evaporator. All solid wastes, including the solidified residue from the evaporator, are disposed of by shipment to a licensed dispos 1 contractor.
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1-3 3/87 1.2 Site and Facility Description 1.2.1 General A general view (looking toward the northeast) of the VNC building complex is shown in the aerial photograph, Figure 1.2-1.
The map in Figure 1.2-2 identifies the various areas and structures.
The large group of buildings in the foreground of the photograph is the "100 Area", consisting of laboratories, NTR, shops, the security building, and a warehouse.
In the upper left corner is the "200 Area" with the large domed reactor ' containment building for shut down GETR and its cooling tower just to _ the left. The two l
domes and tall' stack in the upper right corner are the VBWR and'EVESR in the "300 Area".
Both of these reactors are shut down and are partially dismantled. Just in front of this area is seen the man-made reservoir, Lake Lee, and two buildings near the road.
This is the "400 Area", which contains some laboratories and offices.
In the upper center of the photograph is the large cylindrical water storage tank on the hillside. Just below it is a small, fenced area that contains the solid radwaste storage facilities which include an earth-covered bunker for storage of items which require radiation shielding such as irradiated fuel rod segments. The meteorological station is located on a hill just to the right of Lake Lee and is visible near the right edge of the photo.
The industrial and sanitary wastewater treatment plant and retention basins are located at the lower left corner of the site and are not visible in this photograph but can be identified on the map in Figure 1.2-2.
1.2.2 Site Lccation Vallecitos Nuclear Center (VNC or the Site) is owned by the General Electric Company and is situated near the center of the Pleasanton Quadrangle of Alameda County California. The nearest towns are Pleasanton and Sunol within a 5-mile radius, and Livermore within a 10-mile radius of the Site.
The VNC is east of San Francisco Bay, approximately 35 air miles east-southeast of San Francisco and 20 air miles north of San Jose.
Figures 1.2-3, 1.2-4, and 1.2-5 show the general Bay Area, the Pleasanton Quadrangle, and the VNC, respectively.
1-10 3/87 Uater is supplied from the Hetch Hetchy Aqueduct by means of a 14-inch line Installed pumps are capable of supplying 1,000,000 500,000-gallon storage tank is provided on the laboratory site; gallons per day A
l gallons are reserved for fire protection.
100,000 Electrical power is supplied by the Pacific Cas and Electric Company to the main laboratory substation from whence it is distributed to each building on the site.
A sewage treatment system is provided at the southwest corner of the site Effluent from this system is disposed to site land.
1.2.4 Democranhv One contributing factor in the selec. tion of the VNC site was residential population in the immediate vicinity is very low. that the 18 houses within approximately 2 miles from the GETR facilities (see Figure There are only 1.2-6).
The number of residents in these nearby houses is approximately 70 The population estimate for a 3-mile radius from the site is less than 1 500 miles southwest of the site.-- about 800 of these people in the town of Sunol, which is shown in Table 1.2-1; the map in Figure 1.2-7 shows the population sectors The population data are taken from the GETR Environmental Information R NEDO-12623 (1976).
- eport, The nearest population center, i.e., a city with a population (1980) great than 25,000, by Livermore located approximately 6 miles northeast from the site er population of 48,349 Fremont (population 131,945) is the other town that has a
a large population within 10 miles of the site.
located in the southwest and west-southwest sectors in the 5-to 10 milA portion of Fremo annulus.
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l-21 3/87-A shielded in-floor dry storage pit is located immediately adjacent to the Radioactive Materials Laboratory water storage pool for temporary storage of irradiated fuel assemblies, rods, or other irradiated material.
1.2.7.2.2 Basement The basement of Building 102 was formerly occupied by the Advanced Fuel Laboratory (AFL) and later the Fuel Fabrication Laboratory (FFL). The AFL was engaged in research and development of plutonium and mixed-oxide fuels. All potentially plutonium-contaminated equipment (e.g., glove boxes and fume hoods) has been removed to a DOE facility, and the laboratory and associated rooms have been decontaminated thoroughly for alpha-emitting isotopes. The FFL was a uranium fuels development facility employing low-enriched uranium.
All activities involving SNM have been discontinued.
l An area that was an analytical laboratory facility in support of the AFL is located on the main floor of Building 102. Again, all large plutonium contaminated equipment has been removed to a DOE facility; the area has been decontaminated for alpha-emitting isotopes and converted into a " hot" shop used in support of RML.
1.2.7.2.3 102 Annex The Building 102 Annex (see Figure 1.2.8) currently houses a shielded cell used for the assembly of californium neutron sources, nonradioactive shops that support the hot cell facilities, and site shipping and receiving facilities.
Inside the shielded facility is an 8-inch diameter, 6-foot deep storage pit.
1.2.7.3 Building 103 A second major laboratory building in the 100 Area is the Metallurgy, Chemistry, and Ceramic Laboratory - Building 103.
This two-story building consists of laboratories, variously equipped with laboratory apparatus designed to handle relatively low-level quantities of radioactive materials, and offices.
The functions served by this facility are research, development, and analytical chemistry services.
1.2.7.4 Building 104 1
This building includes shops, offices, and storage space.
1.2.7.5 Building 105 Just north of Building 102 is Building 105.
The principal facilities located in this building are a research reactor (the Nuclear Test Reactor) and laboratories. Offices for the assigned personnel are provided in the building.
1-22 3/87 The Nuclear Test Reactor may serve as a source of neutrons for irradiations, experiments, and as a sensitive device for reactivity measurements. The laboratories in Building 105 use only minute quantities of radioactive materials.
1.2.7.6 Building 106 Building 106 contains maintenance shops, radiation instrument calibration facilities, and the development shop. Radioactive materials are brought to the development shop as encapsulated devices for equipment or mechanical modification and radiography.
1.2.7.7 Area 200 This entire area was the GETR facility.
The reactor was placed in a cold shutdown condition in October, 1977. The last fuel was shipped from the facility in October, 1982.
The facility is deactivated, and a " possess only" license (TR-1, Amendment No. 14) was issued in February, 1986. The license l
authorizes possession of the by-product material as may have been produced by operation of the reactor. No source or special nuclear material is authorized.
1.2.7.8 Area 300 Originally, this was the VBWR facility.
Later, the EVESR facility was added to the area.
Both facilities have been deactivated for over 15 years.
The support facilities have been modified to provide laboratory, test and storage facilities, and office space. The radioactive liquid waste evaporator plant is located in this area adjacent to the deactivated VBWR site.
1.2.7.9 Area 400 The 400 Area includes two buildings, 400 and 401.
Building 401 is devoted to offices and laboratories. Building 400 formerly contained an experimental low-enrichment uranium scrap recovery system, and there were some activities that involved by-product material licensed by the State of California. All activities involving SNM have been terminated.
Building 400 experiment areas have been decontaminated to a nonsmearable condition.
1.2.7.10 Solid Radioactive Waste Storage Facility Solid radioactive wastes generated at the various laboratory and facility locations are stored in the waste storage facility located approximately midway between the VBWR and CETR areas.
Shielded storage facilities consist of horizontal tubes for storing 5-and 7-inch diameter waste liners.
1-23 3/87 1.3 Process Descriotion 1.3.1 Ceneral A large variety of processes are used in the many research, development, and production activities carried on at VNC.
Typical processes performed at the primary VNC facilities are discussed below. More detailed information has been provided to the Commission in the documents listed in Appendix A.
As stated regarding the facility descriptive information, repeating the information already provided or providing more specific references in this document are not warranted.
1.3.2 Building 102 i
This building contains one of the more important facilities that uses processes involving radioactive materials -- the Radioactive Materials Laboratory (RML).
Based on the materials and archods of construction of the RML Hot Cell complex and the equipment and materials handled and stored therein, a conflagration is not possible nor is a structure damaging explosion.
In fact, only small localized fires would be possible in the Hot Cell complex.
Studies performed under the direction of the NRC have concluded that loss of Hot Cell contain-ment from natural phenomena events is not possible.
Furthermore, based on VNC's criticality safety program, criticality is possible in any Hot Cell only under all of the following conditions:
a.
triple batching; and b.
introducing water; and c.
reassembling the fissile material into a cube, sphere, or cylinder with a diameter approximately equal to the height; and d.
uniform dispersal (or clumped for s 5% enriched) to achieve optimum moderation; and e.
full water reflection.
Therefore, there is essentially no driving force available to disperse radioactive materials from the cell complex thereby creating a radiological emergency.
1.3.2.1 Radioactive Materials Laboratory Typical processes performed in the RML facilities are:
a.
Routine physical processes such as visual examinations, remote disassembly, physical measurements, gamma scanaing, mechanical testing, ultrasonic and eddy current testing, and metallographic examinations of reactor hardware and fuel.
1-24 3/87 b.
Fission gas collection by puncturing fuel element cladding, c.
Dissolution for fuel burnup analysis.
d.
Microdrilling to removo fuel for burnup analysis, e.
Photographic processing.
f.
Decontamination.
g.
Radioisotope processing.
I 1.3.3 Building 103 This building contains general chemical and metallurgical laboratories in which only relatively low-level radioactive materials are used. Approximately half of the building is office space. The work performed in these laboratories is of a diverse nature typical of a research and development facility such as:
Radiochemistry processes involving isotopic analysis, activity a.
determinations and studies of the behavior of radioactive materials in various simulated environments and under controlled conditions, b.
A complete radiological counting laboratory with a wide variety of instruments used for assaying the radioisotopes produced commercially at other VNC facilities and the many analyses involved with the monitoring and surveillance programs.
At the conclusion of experiments, radioactive materials are reworked, reused, l
stored, transferred off site to authorized persons, or discarded as wastes.
No isotopic separation or processing of special nuclear material are conducted except as necessary for experimental and analytical purposes.
Safety considerations include positive control of limited quantities and typeu of samples being handled. Only standard analytical procedures are carried out in the glove boxes and hoods. Toxic or flammable chemicals are allowed and l
used only in limited quantities.
Liquid waste streams resulting from the laboratory procedures are analyzed and transferred to the waste treatment facility at Building 349.
l A storage vault is provided on the ground floor of the building for storage of l
Specific limits are established and imposed on the storage of SNM for criticality, accountability, and safeguards control.
l A satellite irradiation facility, Building 103A, is located just north of Building 103 for the handling of Co 60 pin radiation sources with an activity of approximately 3 x 10* CL.
The sources are located at the bottom of a deep, water-filled pit and serve for irradiation of equipment and materials under special study. The water used for shielding the sources is treated using
1-25 3/87 filters and ion exchange columns, and automatic control of the proper water level is maintained.
A radiation detector located above the pit is equipped with an alarm to warn of a drop in shielding water level.
The facility is locked, and all entries are made on a controlled basis.
A radiological evaluation assuming the loss of all material at risk authorized for this building resulted in site boundary consequences less than the lowest EPA PAC values.
1.3.4 Buildine 104 This building conta'.ns facilities such as storage rooms, electrical shop, and carpentry shop.
There are also several offices in the building. Radioactive material in DOT Specification shipping containers and small scaled sources contained in equipment may be stored in this building. The contained radioactive material in Building 104 is judged not to be material at risk.
1.3.5 Buildine 105 This building contains the Nuclear Test Reactor (NTR), two vault-type rooms, special measurement laboratories, and offices. At the present only the NTR facility uses significant amounts of radioactive materials.
1.3.5.1 Nuclear Test Reactor The NTR is a heterogeneous, enriched uranium, graphite moderated and reflected, light-water-cooled, thermal reactor licensed to operate at powers up to 100 kW (thermal). The core is cooled by either natural or forced circulation of deionized light water circulated in an aluminum primary syatem located inside a heavy concrete, thick-walled, shielded cell.
The reactor is a variable level neutron source used in the research, development, analytical, and commercial programs of General Electric and its customers.
Presently, the reactor is used primarily for neutron radiography work; however, other potential uses are:
Reactivity measurements of fuel and structural materials for quality a.
control purposes.
b.
Variable neutron source for nuclear detector research, development, and quality control, c.
Radiation effects studies.
d.
Limited isotopes production.
l Analyses show that fuel melt is not possible from loss of coolant from the NTR.
1-26
-3/87 1.3.5.2 Vault-Type Rooms Neither of the two vault-type concrete-shielded rooms in Building 105 is used l
for radioactive materials work or storage.
l 1.3.5.3 Laboratories l
Several laboratory areas in Building 105 contain equipment for research and l
special measurement activities. This work involves minimal amounts of radio-activo material used in conjunction with the following types of equipment:
j a.
Mass Spectrometers b.
Scanning electron microscope f
c.
X-ray diffraction machine d.
Electron microprobe i
e.
Ion microprobe A radiological evaluation assuming the loss of all licensed material at risk authorized for this building resulted in site boundary consequences much less than the lowest EPA PAG values.
1.3.6 Buildine 106 This building houses the machine shop, instrument shop, development shop, an l
x-ray room, radiation instrument calibration room, and offices. The shops currently are equipped with machine tools, furnaces, welding equipment, leak detectors, controlled atmosphere chambers, hand tools, and other conventional shop equipment.
l
1-28 3/87 1.3.8.1 Building 300 In this building mechanical properties of irradiated Zircaloy are analyzed and radiochemistry training classes are conducted. On occasion, low levels of radioactive materials may be handled in designated building areas.
1.3.8.2 Building 302 Cas technology development operations were conducted in Building 302. Testing operations were conducted for filtering and trapping fission gases. These operations which utilized microcurie to millicurie quantities of gases have been discontinued. The deactivated equipment remains in storage.
1.3.8.3 Building 349 Liquid waste evaporator operations are conducted at Building 349.
Low-level radioactive liquid wastes are collected from various site areas and transported in a portable 1,500 ga13 cn tank to this facility for processing.
The contents of this portable tank are pumped to a 5,000 gallon evaporator feed tank. The concentrates from the evaporation process are transferred into Department of Transportation (DOT) Specification 55-gallon drums and solidified with diatomaceous earth and cement.
These solid wastes are stored l
temporarily at the waste evaporator area, then delivered to the solid radwaste storage facility prior to off-site shipment.
Processing is on a batch basis, and approximately 800 gallons of liquid waste per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> shift can be evaporated. Tanks which originally were part of the VBWR/EVESR tank farm are located in close proximity to the waste evaporator area and are used for interim storage of surplus low radioactive concentration liquid wastes. The off gas stack for the facility is equipped with absolute filters and a stack monitor. A radiological evaluation assuming the loss of all material at risk authorized within this area resulted in site boundary consequences less than the lowest EPA PAC values.
l 1.3.9 Aren 400 1.3.9.1 Building 400 A small pilot plant operation for the recovery of low enriched (s 4%) uranium from unirradiated fuel scrap material was located in a high bay laboratory addition to Building 400. All activities involving SNM have been terminated.
The process system has been dismantled and will be disposed of.
The building has been partially decontaminated.
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D 2-1 3/87 2.0 ENGINEERED PROVISIONS FOR ABNORMAL OPERATIONS Facilities at VNC are designed, equipped, and maintained to perform complex, diversified research, development, and production activitios that involve hazardous processes and materials. This section contains information about the process and control measures that contribute to (a) preventing or mitigating the consequences of incidents, (b) promptly detecting accident releases of radioactive materials, (c) effecting corrective or mitigating responses, and (d) safe and prompt recovery actions in the event of abnormal operations.
2.1 Criteria for Accommodation of Abnormal Ooerations Design criteria at VNC are based on the premise that it is more desirable to prevent an accident than to reduce the effects of ona that has occurred.
However, the safety measures applied shall strike a balance between preventive and palliative measures consistent with the identified potential safety hazard.
In the project design stage, the range of operating conditions for the proposed plant or activity are determined, plant and equipment reliability and expected lifetime requirements are established, critical components are identified and measures taken to reduce the probability of critical component failure consistent with the identified potential safety hazard.
The design, fabrication, installation and operation of facilities and activities conducted therein must conform to standards which, on the basis of experience, are judged by competent specialists to yield an acceptable level of safety.
Safety features must be provided (at least in part) to make the probability of an injurious accident involving VNC products or operations so small as to be negligible from the point of view of the individual member of the public and j
of the individual employee.
t Operations involving radioactive materials must be designed, equipped, and conducted to provide the maximum practical protection of personnel and the surrounding environment against the hazards of ionizing radiation. The safety features selected must take into account the nature of the operation, the i
radionuclides involved, and the quantities available, i.e., the safety features must be provided consistent with the identified potential safety hazards.
There will be some facilities, equipment, and activities at VNC for which criteria, in addition to the general critoria listed below, must be identified and satisfied in the interest of public and employee safety.
l
o 2-4 3/87 l
l l
c.
Facility supervisi,.n/ management or the EOC would request radiation monitoring and radiological engineering assistance as appropriate from the nuclear safety component.
d.
Nuclear Safety personnel will assist the Building Emergency Team (see Par. 4.2.2.6) in performing the necessary radiation surveys and l
evaluations to assess the extent of the release and will advise operations regarding such things as:
(1) adequacy of corrective action; (2) special facility and personnel surveys required as a result of the release; l
(3) radiation protection aspects of recovery actions.
2.1.3 Suncort Systems The principal service and support systems are:
o Ventilation o
Confinement i
i o
Electrical o
Compressed Air and Canes o
Water o
Cold Chemical a.
Ventilation Ventilation systems incorporate liigh Efficiency Particulate Air (HEPA) filters whenever licensed material is handled at VNC. The significant activities where licensed material has a potential for contaminating the ventilation air are in Buildings 102 and 103.
These two locations are the primary ones where licensed material is handled in unencapsulated form or in single-wall containers.
The ventilation systems condition the air supply, direct airflow from office areas to areas of progressively higher potential for contamination, and filter the exhaust to the environment through one l
to three stages of liigh Efficiency Particulate Air (HEPA) filters.
l l
t
2-5 3/87 (1) System Canneities and Flow Direction.
The supply system and exhaust fans operate in a push pull mode at a capacity sufficient for the design flow rates of the systems.
Final exhaust from Building 102 is normally 40,000 cfm and can be increased to 50,000 cfm during abnormal conditions; the system is designed to handle a maximum of 100,000 cfm.
Final exhaust at Building 103 is normally 40,000 cfm during working hours and 20,000 cfm during nonworking hours; the design value is 40,000 cfm. The system backflow preventers, dampers and flow paths are adequate to direct airflow from areas of lesser to areas of higher potential for contamination. The operating areas are supplied at a minimum of six air changes per hour and a maximum of 40 changes per hour, which is approp riate to minimize occupational exposures.
(2) Air Pressure and Balance.
Small static negative pressure differentials with respect to the atmosphere (0.01 to 0.03 inches of water) are maintained for the isolation of general work areas.
Intermediate negative pressure differentials (0.02 to 0.04 inches of water) are used to isolate hot cells.
Maximum negative pressure differentials (from 0.50 to 1.0 inches of water) are used at the glove boxes to maintain contamination control and to assure the maintenance of minimum air velocities (125 ft/ min) across any opening during normal or accident conditions. Appropriate instrumentation to indicate airflow direction and/or differential nressure is provided.
Operating area managers have the res,..sibility to assure that air pressure and flow balances are maintained for the ventilation systems in their area.
g3) Emercency Safety Features.
If normal electric power fails, an emergency diesel-generator unit is started automatically at Building 102 to maintain operation of essential ventilation components and associated monitors, samplers and alarms. At Building 103 there is a standby motor and exhaust fan in case of failure of the normal fan or motor.
In the case of power loss at Building 103, operations are secured and the building is evacuated.
Emergency power is not available for monitors, alarms and samplers at Building 103.
i l
(4) Air Filtration. Glove boxes have High Efficiency Particulate Air (HEPA) filters on all air inlet and outlet ducts.
In Building 102, the Radioactive Materials Laboratory (RML) exhaust ventilation from the hot cells passes through a roughing and HEPA filter at the cell wall, through an inter-i mediate single stage bank of 10 HEPA filters, and through a single-stage bank of two activated charcoal filter beds for iodine removal, if necessary, before release through the final exhaust system consisting of a single-stage bank of 30 HEPA l
1 filters and a 75 foot stack at Building 102A.
o 2-6 3/87 In Building 103, air is drawn from the hoods and glove boxes through individual HEPA filters at each outlet. The exhaust flow then is passed through a final stage of 20 HEPA filters l
and discharged through a 48 foot stack.
(5) Filter Testine. All ventilation system final exhaust HEPA filters for facilities that use licensed material are dioctyi sebacate (DOS) testable and must pass routine DOS tests of 99.97% efficiency for a single filter and 99.95% for a filter
- bank, b.
Confinement Primary barriers for radioactive confinement are provided by the process equipment; sealed canisters; sealed plastic bags; or hoods, cells, or glove boxes.
The hood, cell, and glove box systems work with the ventilation system described previously so that leakage of air is inward.
The secondary confinement barrier consists of rooms, building walls, and the building ventilation systems.
The exterior walls are of concrete or cinder block construction, and the roofs are flat decking covered with a top coating of gravel, c.
Electrient Systems The site is provided with a reliable source of off-site electric power by two feeder lines from a Pacific Gas and Electric Company distribution system to the site's main substation.
Electrical power is required to sustain important safety functions such as exhaust fan operations, alarm systems, other instruments for equipment control, and security operations. Alternate supply systems and emergency generators are used where it is necessary to provide reliable operation of these systems even if off-site power is lost.
In some areas there are battery backup systems for essential alarms.
In radioactive material laboratories where there are no emergency power systems, operating procedures require shutdown and evacuation in the event of loss of power.
2-10 3/87 Filters in the ventilation system of Building 102 are protected by fire detectors that, in addition to alarming, also automatically activate fire suppression systems. The RML hot cell ventilation exhaust HEPA filters, charcoal filters, and the exhaust ducts leading from the RML to Building 102A are protected by coincidence-type detectors (Kidde ATM0 Model 500-1 and Model CSD thermistor tube) or by set point type detectors (MERCOID MX 51-R-153) that activate the fire suppression devices described in the next section.
2.1.3.4.3 Fire Suppression The main source of water for VNC is the 200 million-gallons-per day capacity Hetch Hetchy Aqueduct of the San Francisco Water and Power Department System located approximately 3 miles south of the site.
l A 14-inch line is installed from the aqueduct to the site.
The installed pumps have a capacity of 1,000,000 gallons per day. The Calaveras Reservoir provides backup for the Hetch Hetchy supply.
Availability of water for fire suppression is assured by the location of the drains for the 500,000-gallon domestic water supply j
storage tank.
Pipe drainage from the tank is designed so that the l
bottom 100,000 gallons of water can be used only for fire l
protection.
l Manual fire suppression is provided by the following capabilities, t
a.
Selected site personnel are trained to fight incipient-stage l
fires.
b.
Mutual aid support arrangements with fire departments in the surrounding communities have been organized.
I c.
Portable fire extinguishers are provided in strategic locations l
throughout the site. The extinguisher types are water, dry chemical, Met L-X, and carbon dioxide (CO )*
2 d.
When fires in the RML hot cells are detected, personnel are alerted through the alarm systems to initiate fire suppression action with the extinguishers provided, e.
Adequate fire hydrants and hose houses are provided at butidings throughout the site, including Buildings 102 and 103.
f.
Drop lines with connected hoses are provided at strategic locations in the main buildings, including Buildings 102, 102A and 103.
l I
l i
l
2-11 3/87 l
g.
Final exhaust HEPA filters in Building 102A are protected by a i
manually operated water spray system.
h.
Each ventilation duct leading from Building 102 to the final exhaust HEPA filters in Building 102A is provided with a manually actuated water mist system.
1 Automatic fire suppression is provided in the following locations:
a.
the main buildings, including Buildings 102, 102A and 103, are protected by automatic sprinkler systems; b.
RML hot cell exhaust HEPA filters in the basement of Building 102 are protected by a two-ton Cardox CO fire suppression 2
system controlled by a set of coincidence detectors.
Building 103 relies on the automatic sprinkler system and does not include additional spray protection for the final ventilation J
exhaust HEPA filter system.
2.1.3.4.4 Administrative Controls The fire protection function at Vallecitos Nuclear Center is a component of the Reactor Operations and Support Services unit assigned to Irradiation Processing. An individual is assigned as l
Site Fire Marshal. This individual is responsible for developing fire protection programs, procedures, and evaluations.
In addition, the ultimate responsibility for oporational safety lies with the supervisor or manager of each activity at the site.
2.1.3.5 Shielding Radiation shieldin6 is provided consistent with the requirements of 10CFR20 and the concept of ALARA.
Reference:
Nuclear Safety Procedure 1250, " Engineering For ALARA".
2.1.4 control Ooerations Through strict enforcement of VEC Safety Standards and Standard Operating Procedures for individual facilities or activities, there is rigid administrative control of the design, installation, operation, and maintenance of equipment and structures important to preventing or mitigating the consequences of accidental release of radioactive material.
l
l 2-13 3/87 2.2.1 Process and Suncort Systems Process and support syctems are designed to have a reliability commensurate with the potential hazards involved. Surveillance and maintenance programs l
are utilized to ensure the systems are not degraded. Operator training and strict adherence to written operating procedures are emphasized to minimize operator error. Nevertheless, safety features such as radiation shiolding, l
confinement systems, ventilation, alarms, interlocks, and automatic action systems are provided to further minimize the probability and consequences of a radioactive material release should equipment malfunction or operator error occur.
2.2.2 Alarm Systems and Release Prevention Canability Performance of the alarm and release prevention equipment for various VNC facilities is discussed in the documents listed in Appendix A.
Satisfactory performance during abnormal conditions is considered in the design of such systems. Experience has shown that when abnormal conditions are anticipated correctly, reliable performance under those conditions can be achieved.
2.2.3 Suonort Systems See subsection 2.2.1.
2.2.4 Gmtrol Operations VNC has a safety assurance program which includes (1) provisions for monitoring and auditing plant equipment and procedures for continued safety, (2) for detecting deteriorating safety performance, and (3) for identifying where improvements are needed.
2.2.4.1 Area Managers The Manager, Irradiation Processing (IP), as the designated responsible safety l
afficer for the VNC site and in conjunction with mana6ers from other l
organizations represented at VNC, has assigned various operating managers l
certain responsibilities for the safe control of nuclear (criticality) and radiation / contamination type activities conducted in their areas and has designated these assignees as " Area Managers".
Some of the responsibilities and minimum qualifications for Area Managers are specified in License SNM 960, Appendix A. Section 4.0 and in Vallecitos Safety Standard 1.3, " Area Manager's Safety Charter".
l Assigned responsibilities of Area Managers have the objectives of making the probability of an injurious accident involving VNC products or operations so small as to be negligible froni the point of view of the l
public and the employce.
Inherent in this objective is the goal to make I
a
2-14 3/87 every reasonable effort to maintain exposures and effluent releases "As Low As Reasonably Achievable" (ALARA) and to comply with appropriate licenses and regulations governing the area's licensed activities.
Each Area ManaSer is responsible for:
1.
The safe operation and control of activities in his assigned criticality and radiation areas and for the safety of the environs as influenced by these activities.
2.
Being knowledgeable of the VNC radiation protection program, the VNC criticality safety program, and the VNC emergency preparedness and response program as these programs apply to his assigned area.
Implementation and detailed guidance for the program requirements are provided by the Vallecitos Safety Standards and through independent review and consultation activities (both formal and informal) by the site Nuclear Safety function.
3.
Compliance with license and regulatory requirements applicable to his assigned area of responsibility.
4.
The development and maintenance of criticality control, radiation i
protection, and emergency preparedness and response procedures for his assigned area of responsibility as appropriate.
5.
Assuring that employees and visitors working in his assigned area have received appropriate instruction in criticality and radiation safety, plant operations, and emergency procedures prior to working with or around radioactive materials in his assigned area.
6.
Assuring that all radioactive materials within his assigned areas are authorized by an appropriate license and/or internal authorization.
7.
Advising the Nuclear Safety ccaponent of proposed and actual changes in facilities, activities, and radionuclidic inventories (including nuclide chemical forms) in his assigned area of responsibility.
8.
Emergency preparedness for all emergencies occurring in his assigned criticality and radiation areas.
2.2.4.2 Nuclear Safety Function Although responsibility for safety han been placed upon area management, other VNC organizational components make contributions to safety in design, support, and analytical work. Centralization of many of the safety functions relating to work involving ::adioactive materials occurs in the j
Nuclear Safety function. Responsibilities and staffing requirements for I
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2-16 3/87 2.2.4.3 Vallecitos Technological Safety Council The Manager, Irradiation Processing (IP), in conjunction with managers from other operations at the Vallecitos Nuclear Center (VNC), has established an on site, independent safety review organization, the Vallecitos Technological Safety Council (VTSC). Membership consists of senior nuclear safety, industrial safety, facilities operation, and engineering personnel.
Responsibilities and membership requirements for this group are specified in License SNM 960, Appendix A, Par. 4.4.
(The VTSC originally was called the I.aboratory Safeguards Croup.) The VTSC is responsible to the Manager, IP; and its recommendations concerning cperations at the VNC site must be implemented unless the Manager, IP, grants relief from them.
For organizations located at VNC not under the direct operational control of the Manager, IP, relief may be requested in writing from the Manager, IP.
If satisfactory resolution is not obtained, higher levels of management shall be used to resolve the differences. The VTSC advises the Manager, IP, reliably, imaginatively, and effectively on matters affecting the nuclear safety, industrial safety, and safety related regulatory comrliance aspects of the VNC site and of the people assigned to it.
The VTSC is an independent review body for all activities at VNC and makes reviews as required by licenses; as requested by operations management, by site nuclear and/or industrial safety components; or at its own initiative.
The VTSC has jurisdiction to review:
(1) reportable incident investigations; (2) unreviewed safety questions of proposed facility changes; (3) operating standards; (4) experiments; (5) receipt, possession, separation, use, processing, and transfer of radioactive material; (6) proposed new criticality procedures or methods of evaluation for operations at VNC; (7) new major factitties proposed for the VNC site; and (8) processes, operations, and procedures which involve toxic, flammable, etc., materials. The VTSC evaluates the overall effectiveness and relevance of safety studies and nuclear safety review activities as they collectively influence safety
)
conditions at the Vallecitos Nuclear Center. The VISC provides expert advice and counsel, but it is not responsible for conducting routine reviews. The VTSC reports its deliberations and recommendations to the Manager, IP, with l
copies to senior site management and affected operating managers. Affected operating managers must reply to VTSC recommendations in writing addressed to the manager of the Nucioar Safety component. The Nuclear Safety component maintains records of the VTSC recommendations and follow on action by operating components.
3-1 3/87 3.0 CIASSES OF RADIOIDCICAL CONTINCENCIES 3.1 classification system The Area Managers of VNC facilities and the Emergency Operations Coordinator have primary responsibility for event assessment. This responsibility includes taking prompt action to evaluate any potential risk to personnel health and safety both on site and off site.
If warranted, the Manager, IP, l
or his representative will make timely recommendations to the Alameda County authorities concerning off-site protective measures. Since on site protective measures could be needed immediately after determination that a hazard exists, prompt event assessment at the source is important.
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l The NRC has established four classes of emergencies.
In ascending order of l
seriousness, they are:
o Notification of Unusual Event o Alert o Site Area EmerEency 1
General Emergency i
o I
l The four levels provide a gradated system in which each level assures fuller response preparations for more serious indicators. The purpose of the
)
Notification of Unusual Event and the Alert classes is "to provide early and l
prompt notification of minor events which could lead to more serious j
consequences given operator error or equipment failure or which might be indicative of more serious conditions which are not yet fully realized".
1 These notifications are made to the appropriate site emergency response i
i organizations. The Site Area Emergency class reflects conditions where some significant releases are likely or are occurring but where a more serious situation is not indicated based on current information.
In this situation, county authorities are notified; and emergency response teams and emergency communications are activated. The General Emergency class involves actual or imminent substantial facility degradation with the potential for releases of large inventories. The immediata action for this class of emergency is staying inside rather than evacuation until an assessment can be made that (1) an evacuation is indicated and (2) an evacuation, if indicated, can be completed before a significant amount of radioactive material has been j
- released, i
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o 4-1 3/87 4.0 ORGANIZATION FOR CONTROL OF RADIOLOGICAL CONTINGENCIES In this chapter the radiological contingency organization is described.
Authorities and responsibilities of key individuals, groups and organizations are discussed.
m 4.1 Normal Plant Organiention The Vallecitos plant site provides working space for many company organizations. The site facilities are administered and maintained by Irradiation Processing (IP), which is itself a production entity.
Included in IP's responsibilities are site-wide services such as nuclear safety, environmental protection, security, facilities maintenance, and emergency planning.
On site organizations are:
Irradiation Processing Advanced Nuclear Applications Reactor Operations and Support Services Nuclear Safety Radioactive Materials Services Remote llandling Operation Marketing BWR Technology
- Chemical Products Technology & Development Process and Radiation Chemistry Fuel Materials Technology
- Parent or6anization; not located on site.
e 4-2 3/87 Relations Operation
- Occupational Medical Programs Nuclear Outage Services
- l Radiological and Special Services Nucles.r Training and Technical Ser/ ices
- Mechanical and Nuclear Training Services l
Financial Planning
- IP Accounting In addition to the manager of IP or his designated alternate, the Specialist-l Facilities Protection Area Managers and BEC** may declare an emergency of any classification upon receiving input of emergency conditions. These positions are empowered to initiate the appropriate radiological contingency response.
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- Parent organization; not located on site.
- Building Emergency Coordinator (see Section 4.2.2.6).
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4-3 3/87 4.2 On-Site Radioloelcal Contineenev Resoonse Oreanization The Emergency Control Organization shall be as shown in Figure 4 1.
From the inception of an emergency, an Emergency Operations Coordinator (EOC) is recponsible for coordinating emergency response activities. At VNC, the organizational structure provides for an initial response phase and a secondary response phase for all emergencies.
Responsibilities of members of the Emergency Control Organization, VNC management, and support specialists shall include those listed below.
Additional responsibilities and duties may be assigned in the implementing l
procedures.
4.2.1 Direction and Coordination 1
4.2.1.1 Hanager, Irradiation Processing (IP)
The Manager, IP, is the senior CE employee on site, lie or his delegated alternate has overall responsibility for emergency response and preparedness activities at VNC. His authority extends to that of enjoiner; and in the face of conflict or indecision, his judgment is final.
The responsibility and authority for directing and coordinating emergency response activities are assigned to Emergency Operations Coordinators (EOC).
Duties and authorities of the EOC durin6 initial and secondary phases of an emergency are discussed below.
4.2.1.2 Emergency Operations Coordinator The on duty Specialist Facilities Protection is the Initial Response Emergency Operations Coordinator (EOC) for all emergencies at VNC.
Specialists Facilities Protection are CE employees trained for implementing and coordinating emergency response activities and assigned to provide continuous coverage at VNC on a three shifts per day, seven days per week schedule.
In the extremely rare instances when the regularly assigned Specialist, Facilities Protection (S FP), is to be absent from the site or otherwise unavailable for emergency response, the Secondary Response EOC (for multiple facility emergencies) will be notified that he has Initial Response EOC responsibilities during the S FP's absence. The name and phone number of the Secondary Response EOC will be posted at the emergency communications center.
Manager, IP, or his emergency response alternate is the Secondary Response EOC.
The Manager IP's alternate for Secondary Response EOC for a single facility l
emergency is the Area Hanager assigned responsibility for emergency response for the involved facility.
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44 3/87 i
INITIAL RESPONSE TRANSFER OF SECONDARY RESPONSE EOC*(1)
. N RESPONSIBILITY EOC*(2)
I I
i I
I I
I I
MANAGER j
BUILDING REACTOR MANAGER SPECIALIST EMERGENCY OPERATIONS NUCLEAR COORDINATORS
& SUPPORT SAFEGUARDS SAFETY SERVICES I
I BUILUING FIRE, ELECTRICAL, SECU4ITY DOSIMETRY, 4
EMERGENCY
& NATURAL PHENOMENA EMERCNCY DECONTAMINATION, TEAMS EMERGENCY TEAMS TEAM
& ENVIRONMENTAL j
EMERGENCY TEAMS
.l 1
ANCILLARY-ADVISORY FUNCTIONS PUBLIC MAINTENANCE /
COMMUNICATIONS MEDICAL 1
RFtATIONs REPAIR I
MANAGER CENTRAL OCCUPATIONAL REACTOR l
ALARM HEALTH NURSE COMUNICATIONS OPERATIONS STATION REPRESENTATIVE
& SUPPORT I
SERVICES i
l j
- Emergency Operations coordinator
}
(1) Specialist, Facilities Protection.
(2) Manager, IP, or his emergency response alternate who is:
(a) Area Manager of involved facility for single facility emergencies.
(b) IP manager, determined from the succession list, for multiple-i facility emergencies.
i Figure 4-1.
VNC Emergency Control Organization i
l
4-5 3/87 For a multiple facility emergency, the Manager-IP's alternate for Secondary Response EOC is the IP manager determined from the IP Manager Succession List below. The emergency response alternate will be the manager whose name is highest on the list that is present at the site.
If none of the managers are present, call-in will be according to the Succession List.
Succession List for Secondary Response EOC 1.
Manager, Reactor Operations & Support Services 2.
Manager, Radioactive Materials Services 3.
Manager, Advanced Nuclear Applications The Emergency Operations Coordinator (EOC) has the responsibility and authority for the following:
1.
Initiation and implementation of the site emergency procedures and coordinating the emergency response activities of the Emergency Control Organization (and off-site assistance) for the duration of the declared emergency.
2.
The Initial Response EOC shall coordinate activities until relieved by the Secondary Response EOC; his duties and responsibilities include:
a.
Assessment of the indicated or reported situation and initiation of whatever action is deemed necessary to minimize personnel injury and property damage.
b.
Prompt notification of the Secondary Response EOC if needed. Upon request by the Secondary Response EOC, initiate actions such as designating the location of the Emergency Support Center (ESC);
notification of Manager, IP, and other Emergency Control l
Organization members, or off-site support agencies or personnel; and initiate implementation procedures.
Provide a status report and relinquish command to the Secondary c.
Response EOC when he arrives on site.
3.
Upon arrival on site and receipt of a status report from the Initial Response EOC, the Secondary Response EOC assumes all E0C responsibilities for implementation of the site emergency procedure and coordinating emergency response activities; his duties and responsibilities include:
1 a.
Activation of emergency teams, if needed, and coordination of their activities.
b.
Notification of appropriate management representatives, ancillary-advisory function personnel, and off-site agencies.
4-7 3/87 4.
Establish surveillance procedures, including periodic tests to ensure the operational readiness of the emergency equipment. Maintain records that i
demonstrate compliance with the procedures for at least 2 years from the time of performance.
5.
Develop and maintain current assigned emergency procedures.
6.
Assign skilled craftsmen as members of the Building Emergency Teams.
7.
Coordinate a11' activities pertaining to site and facility fire protection and fire fighting.
4.2.2.3 Senior Licensing Engineer Senior Licensing Engineer is responsible for the following:
1.
Develop and update emergency procedures pertaining to the release of information to the news' media.
2.
Serve as Confrontation Team Coordinator for the implementation of the confrontation procedure.
, 3.
Serve as VNC Communications Representative for providing information about the emergency to the communications and public relations function for release to the news media.
4.2.2.4 Occupational Health Nurse The,0ccupational Health Nurse has the following duties and responsibilities:
1.
Provide medical assistance as required during the emergencies.
2.
Coordinate arrangements for admissions to hospitals and for obtaining ombulance service or other transportation.
3.
Obtain written agreements regarding the treatment and transportation of injured persons that are radioactively contaminated.
t 4.
Obtain medical assistance, equipment, and supplies as required.
5.
Maintain the emergency medical supplies, i
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4-8 3/87 4.2.2.5 Area Managers l.
Area Managers are designated by the Manager, IP, in VSS 1.3.1, " Area Manager l.
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Assignment Listing". Where more than one Area Manager is assigned to a-building or. area and it'is unreasonable for each to issue procedures, maintain an emergency team, etc., one of them.is assigned.the responsibility-for coordinating these activities. Area Managers are assigned the following.
duties and responsibilities:
1.
During the absence of the Manager, IP, serve as.the Secondary ~ Response 1
EOC for single facility emergencies (fire, criticality, high radiation levels, bomb threats, etc., involving only their e.ssigned areas).
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4 2.
Establish written procedures as necessary to provide-the' additional details necessary to implement the site emergency plans and procedures 4
for their area (s) of responsibility.
3.
Maintain in operational readiness-the equipment and personnel require'd to implement the site ~ emergency plans and implementing procedures for their area (s) of responsibility.
4.
Appoint a, Building Emergency Team, including a Building' Emergency; Coordinator who is the emergency team leader, for their area (s) of responsibility.
5.
Education and training of all assigned personnel for proper emergency.
response in their area (s) of responsibility.
i 6.
Hold drills and exercises as necessary to demonstrate = the ' effectiveness of emergency procedures and training and.the availability and operational readiness of equipment for their area (s) of responsibility.
n 7.
Provide and update response procedures for the-Site Alarm Systems-Action Book, located at the emergency communications center, for each alarm from his assigned area (s) connected into the system.
a 3'l 4.2.2.6 Building Emergency Teams Area Managers will ensure there is a Building Emergency. Team (BET) appointed j
for each building or area for which he has emergency response responsibility.
j Minimum functions on each team will be team leadership, an assembly area control, fire. suppression, and first aid; in addition, where warranted by the-nature of the facilities, there may be additional functions (e.g., radiation monitoring and equipment operation and service). There'will be at least one-i alternate designated for each function.
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1 s
1 l
e s.
4-9' 3/87:
!The BEC is-the team leader and has the following duties and responsii>ilities':
1.
Assure the'. emergency team is properly equipped and trained to responc to l
-emergency situations in their. assigned area.. Promptly report any deficiencies in the training or equipment to the Area Manager.
2.
Immediately investigate and evaluate emergency or potential emergency situations for his assigned area.
Initiate whatever. action deemed suitable.to minimize personnel injury or property damage. lesponse may include initiation of the site emergency procedure.
3.
Direct the Building Emergency Team and other personnel at the site in the performance of emergency response actions specified in the site einergency procedures and the local implementing procedures or as directed by the
-EOC.
4.
Maintain close communication with the EOC to coordinate the BET activities with special emergency' teams and other support personnel.
Assigned members of the BET have the following responsibilities:
1.
Be familiar with their assigned duties and-responsibilities-in the site emergency procedures and local implementing procedures, and fulfill these obligations during emergencies and drills.
2.
Participate in the training programs, drills and practices as required.
3.
Promptly report to the BEC any observed deficiencies in training, emergency procedures, or equipment.
4.2.2.7 Ancillary-Adviscry Functions Some specific responsibilities are assigned to the ancillary-advisory.
personnel shown in Figure 4-1.
Generally,.they will receive a request to participate and be given instructions by the EOC or the BEC.
Some general responsibilities are listed below:
a.
Upon receiving notification from the EOC, assigned personnel shall respond as requested.
b.
Personnel assigned to the emergency communications' center shall:
1)
Receive and record information pertinent to the emergency situation and keep the EOC and other components of the-Emergency Control Organization up to date.
4-11 3/87 4.3.2 First Aid Personnel and Ambulance Services First aid assistance is available on an informal basis from the Alameda County Sheriff's Department and the-State of California Highway Patrol. Normally, contact with these agencies would be by telephone; however, radio communication with the Sheriff's Department is available at the Central Alarm Station (CAS) in the security building (102B).
Ambulance service is available from a privately owned company in Livermore.
During normal work hours, arrangement for transportation will be made by l
telephone by the VNC Occupational Health Nurse. At other times, the arrangement will be made by the Specialist, Facilities Prctection.
4.3.3 Services of Other Medical Personnel On Site A company physician is on site one-half day per week and on call for emergencies. A company nurse is available on site during normal work hours and will be called in for emergencies.
These individuals provide the emergency response.,edical function. There are no other on-site medical personnel.
4.3.4 Fire Finhtine Backuo VNC has fire fighting backup from the participants in the Twin Valley Mutual Aid Agreement. Request for assistance will be made by telephone or radio.
In the event of a request for assistance, first response will be by the California Division of Forestry (CDF).
If additional assistance is needed, personnel and equipment are available from LLNL, Alameda County, City of Livermore, City of Pleasanton, Veterans Administration Medical Center, Dublin-San Ramon Service District, Alameda OES Headquarters, and Camp Parks.
4.3.5 Police Assistance VNC has a formal agreement for police assistance with the Alameda County Sheriff's Department. Assistance is available from the California State Highway Patrol on an informal basis. Communications with either agency can be by telephone and with the Sheriff's Department by radio.
4.3.6 Other None.
4.4 Coordination With Participatine Covernment Agencies VNC is located in an unincorporated area of Alameda County, California.
For this area, the County is responsible for government agency initial response.
Assistance from appropriate state and/or federal agencies is available.
The agencies or organizations for each level of government that may participate are identified below.
4-12 3/87 4.4.1 County The Alameda County Office of Emergency Services (offices at San Leandro, California) is responsible for planning and coordinating actions to prevent and mitigate radioactive material releases.
They will coordinate operations of the county forces with those in which state and/or federal agencies become involved. A County Support Team is composed of representatives of other county agencies that may be requested to participate in the emergency response.
Some of these agencies are listed below, a.
Fire District b.
Sheriff's Department c.
Health Care Services Agency d.
Public Works Agency e.
Flood Control and Water Conservation District f.
Explosive Ordnance Disposal g.
Agricultural Commissioner's Office h.
General Services Agency 1.
Sanitary District 4.4.2 State The State of California is an Agreement State responsible for licensing radioactive materials. The State has assigned responsibility and primary authority over radioactive materials licensed by the State to the State Department of Health Services, Radiologic Health Branch (RHB). The State Office of Emergency Services, when requested, will assist RHB for emergencies involving radioactive materials. OES also serves as a 24-hour answering service for RHB and when requested and able will respond, monitor and provide assessment at the scene of an accident. OES is California's coordinating agency for marshalling state and local resources for declared emergencies requiring state-level coordination. The resources OES can bring to bear include those of the following state agencies:
a.
Department of Health Services, Radiologic Health Branch b.
Department of Health Services, Medical Services c.
Military Department d.
California Highway Patrol
a 5-6 3/87 Preventive measures are implemented, to the extent practicable, to prevent the occurrence of such accidents; and in the event that prevention techniques fail, protective measures are preplanned to mitigate the effects of such accidents. Protection must be provided not only to members of the general public and the community of General Electric employees, out also to members of the emergency response team.
5.5.1 Emergency Exposure Control Procram In order to protect emergency workers from airborne contaminants during and following a serious accident situation, self-contained breathing apparatuses (SCBA) are available in or nearby the buildings which have the potential for high airborne concentrations. The SCBA units are located in strategic places such that they can be donned quickly in an area outside of, but near, the accident scene.
In addition to SCBA units, airline respirators are available both in the full facepiece style and in the fresh air hood assembly style.
These airline respirators are useful for taking corrective actions in areas where airborne contamination level is not immediately dangerous to life or health.
For use in areas where SCBA units are not required and where breathing air supply lines are not available, full facepiece masks with canisters are available. These, too, can be used by emergency team workers, especially in the course of collecting post-accident stack air samples and downwind environmental air samples.
In the facility which handles the greatest quantities of radioactive materials (Building 102), air monitoring during those emergency conditions which have an associated loss of power is sustained by the use of a diesel-powered emergency generator.
Part of the energy provided by the emergency power generator is used to drive exhaust fans which maintain a flow of air into the radioactive materials areas from the surrounding clean areas.
From the radioactive materials areas, air passes through high efficiency filtration systems before it is exhausted from the building.
A portable constant air sampler is available in Building 102B for use in the l
event that air samples are required in areas where no electric utilities are available.
Direct exposures of emergency workers are monitored by remote area monitoring (RAM) devices, portable survey instruments, and by the individual's own personal monitoring instruments. The RAM systems, like the constant air monitoring systems, provide constant monitoring capability; but, instead of providing information abo 9t air concentrations, the RAM's provide information on radiation levels. Whe:e the RAM's are provided with emergency-use power and with proper remote readouts, they, too, provide information about radiological safety conditions within the radiation area without having to enter the area first and use portable survey instruments. A sufficient number of portable radiation survey instruments are provided in each of those buildings which contain radioactive materials.
In addition, a number of portable radiation survey instruments are kept in an emergency supply cabinet in Building 102B. Each emergency team member will carry at least a film badge 1
5-7 3/87 and, when appropriate, a direct-reading pocket dosimeter; and, in some situations, he will carry an alarming dosimeter. The pocket dosimeter is used l
by_the emergency team member to keep track of his own exposure to x-and gamma radiation as he performs the functions delegated to him.
If the alarming dosimeter is used, the individual is made aware that he has received a predetermined amount of radiation exposure whenever the dosimeter alarm is, activated, thus avoiding accidental exposures beyond the levels planned.
Some of the alarming dosimeters have the versatility of being dial-adjusted to indicate the accumulated amount of exposure; in this way, the alarming dosimeter may serve as a check on the direct-reading pocket dosimeter.
Transportation and communication systems are important in emergency response, and both are provided at VNC.
Company transportation is available to certain radiation monitoring technicians (RMT). These RMT's are included in the emergency response teams; and whenever notified of a criticality alarm or other radiological emergency alarm, the RMT responds to the scene of the problem with portable instrumentation to assist the facility RMT and other emergency personnel with the work. The Specialist, Facilities Protection, and the RMT's are equipped with two-way radios in order that information can be transmitted to base radio stations which are located at the emergency communications center and the whole body counting room in Building 102B.
In addition to these radios, other on-duty RMT's and the supervisor of the radiation monitoring technicians carry a two-way personnel-portable radio which provides for fast transmission of information whenever an accident occurs.
5.5.1.1 Exposure Guidelines As a guide for making judgements regarding the amount of exposure to allow a person responding to an emergency to receive while re-establishing radiation control following an accident, the information provided in EPA 520/1-75/001 was used to arrive at the guidance listed in Table 5-1.
Exposure limits for situations involving the gent.ral population and emergency workers are listed
)
in the table. Note that the Suggested Values (SV) listed in Table 5-1 should be used except for situations in which local constraints would make them impractical to use; in those cases, the " Maximum" (Max) values may be used.
However, it is firmly recommended that the Max values are not exceeded.
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5.5.1.2 Ra'diation Protection Program Exposures at VNC are controlled in accordance with Vallecitos Safety Standard 5.2, " Exposure Limits". When immediate action is necessary to mitigate or
'l
. prevent a hazardous situation, the responsible Area Manager or the EOC may authorize entry into. exposure rates greater'than 150 Rem per hour without further approval.
In no case shall planned whole body doses exceed those identified in Table 5-1; that is, 25 Rems for protection of health and property and 75 Rems for saving human life.
5.5.1.3 Monitoring Emergency monitoring to determine doses and dose commitments to personnel at VNC is described in implementing procedures which specifically address the subjects of personnel decontamination, an emergency dosimetry team, and a personnel emergency decontamination team.
5.5.2 Decontamination of Personnel Based on VNC's operating philosophy of no personnel contamination or internal depositions, the action levels for decontamination are based on detectable levels with the instrumentation used for the isotopes of-concern.
Personnel exhibiting the greatest degree of contamination and with the greatest potential for internal deposition from this contamination normally will be decontaminated first unless an unusual case of localized contamination could cause severe damage in the contaminated area; e.g., >> 1.0 pC1/cm beta-gamma 2
or 0.004 pCi/cm2 alpha.
Decontamination methods, supplies, instruments, materials, and procedures are described in implementing procedures as sentioned above. Also, there is a procedure for emergency locker inspection and maintenance.
5.6 Medical Transoortation l
Transport cf injured persons to off-site medical facilities (see - 5.7) will be by private ambulance or Company vehicle (s).
Arrangements for transportation of injured persons are the responsibility of the Occupational Health-Nurse or in her absence the EOC upon determination of severity and urgency.
Individuals who are contaminated and due to medical urgency must be transported prior to decontamination shall be accompanied by a qualified radiation monitor to control the spread of contamination.
6-2 3/87 6.2.3 All-Call System The site All-Call System is a one-way public address system provided for use in making emergency announcements ar.d providing instructions.
This system has speakers so located about the site that all persons, whether inside buildings or about the inner fenced portion of the site, can easily hear them.
6.2.4 High-Level Conference Circuit (HICON) Syst1E The HICON System is an on-site emergency telephone circuit separate from the standard public telephone system. It has stations at the on-site emergency assembly areas and locations convenient for use by key emergency and management personnel.
6.3 Facility For Assessment Teams The EOC will designate facilities to be made evailable for use by the teams performing assessment functions. These facilities will be dedicated to the use of the assessment teams, will be located conveniently near the ESC, and will be provided with public telephones and other needed equipment.
If special facilities are needed by the staff performing post-accident and recovery assessment, they will be designated by the Manager, IP, and equipped as necessary.
6.4 On-Site pedical Facilities An extensive on-site medical facility is maintained at the Vallecitos Nuclear Center.
In addition to the Site Dispensary described in 6.4.1 below, the advantages of the many chemical and radiological analysis laboratories and the whole body counter are noted here.
6.4.1 Site Medical Dispensary The medical facility at Vallecitos consists of five rooms: waiting room, emergency treatment room with a nurse's station, treatment / examination room, a doctor's consultation office, and a bathroom.
It is a full-service, occupational medical facility with a registered nurse trained in occupational health care and capable of giving emergency first aid and basic resuscitation.
There is also a doctor on duty part time who is a specialist in occupational medicine.
Both are on call for after-hours l
emergencies.
The facility can handle two litter patients routinely but can expand to eight-litter capacity in case of an emergency.
In a major catastrophe, the space would be utilized in a designated facility for emergency care. The l
capability exists for providing urgent care and rendering patients transportable when indicated.
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6-5 3/87 6.5.1.5 Eberline AHM-20 The AHM-20 is an AC-operated, wall-mounted, alpha-particle monitor which is used to detect alpha contamination on hands. All of these instruments have been taken out of service.
6.5.1.6 HP-210 and HP-260 The Models HP-210 and HP-260 are similar external hand-held G-M probes with a very thin mica window used for detection of beta radiation (down to 40 kev).
They can be used with any +900-volt portable instrument or laboratory monitor (such as the E-120 and RM-15 meters).
Because of its high sensitivity and high-density tungsten gamma shield, the HP-210 is used for contamination control.
'The HP-260 is the same as the HP-210 except it has a light aluminum case for use in low background areas.
The large open window area of both has a sturdy wire screen to protect the thin mica window.
6.5.1.7 Eberline HP-177 The HP-177 G-M probe for beta and gamma is used mainly for cantamination control.
The HP-177 proba housing has a beta window which can be opened or closed.
Some of the older probes are the 360-degree window probes which have a metal screen covering the tube.
The 1B85 aluminum G-M tube is the most common tube used with the HP-177 on site. A stainless steel tube is sometimes used and can be distinguished by its bluish-purple color, whereas the 1B85 is a shiny aluminum color. The 1B85 is more sensitive than the stainless steel tube.
6.5.1.8 Technical Associates CP Models 4 and 5 The Technical Associates CP Models 4 and 5 are the most common portable, battery-powered dose rate instruments used at VNC.
The CP uses an air equivalent ionization chamber as the detection element.
It uses air at atmospheric pressure as the ionization medium.
6-7 3/87 l
and cadmium shield, higher energy neutrons can be detected. The dual-scale meter has three ranges: 0-800; 0-8,000; and 0-80,003 cpm; and 0-24, 0-240 and 0-2,400 thermal neutrons /cm -sec.
2
' Dose rates can be estimated with this meter by use of a conversion graph if neutron energies are known.
6.5.1.13 Other Monitoring Instruments In addition to the above-listed instruments, there are a few of the same basic instruments on site, such as G-M's, manufactured by other instrument companies. Permanent hand-and-foot monitors are installed at the exits from the major radioactive materials facilities on site.
They detect 'ueta-gamma or alpha activity as appropriate to the facility.
6.5.2 Assessment Systems These systems are used to assess the magnitude and likely dispersion of releases.
6.5.2.1 Water Sampling and Monitoring Systems Four large basins (60,000 gallons) receive the site industrial liquid waste.
In normal operation, no radiological waste enters the system.
Such waste goes into a closed system and is collected in waste. tanks for processing.
The basins represent an excellent collection / retention resource in case of a spill of radiologic wastes into the drain lines. Manual sampling is done on effluents, and any basin could be held until cleanup has been accomplished.
6.5.2.2 Meteorological Monitors The VNC meteorological station is located on a round-topped knoll about 2,000 feet south-southeast of GETR and just south of Lake Lee.
Wind speed and direction are measured by an anemometer and vane atop a pole 45 feet above the terrain. This is at an elevation of about 630 feet above sea level.
The i
speed and direction data are recorded on a two-pen strip chart recorder.
l These records give the general flow patterns of wind over the site. There are two temperature sensors mounted on the pole, one at 20 feet and one at 40 feet above the ground.
These data are recorded on two circular charts. A standard rain gauge located approximately 5 feet above ground level is recorded. All data records collected from the station are provided on a routine basis to the Specialist, Environmental Protection. All instruments are calibrated as necessary.
6-9 3/87 6.5.5.1 Whole Body Counter A whole body counter (shadow shield principle) utilizing a 5x5-inch Nal crystal is capable of detecting 0.01-0.1% of the maximum permissible body burden of several common gamma emitters and 1% for most other gamma emitters.
6.5.5.2 Environmental Monitors Environmental surveillance of gamma radiation levels is provided by a number of dosimeters located on the VNC site and at its perimeter.
Four fixed sample stations to monitor airborne radioactivity also are located on site.
6.5.5.3 Criticality Alarm - LiI Crystal System This monitoring system uses a lithium-iodide crystal optically coupled to a photomultiplier tube.
Failure of any detection circuit component which would prevent criticality detection activates a warning light on the unit.
Failure of any signal-producing component is detected during the quarterly test, l
although most locations are covered by more than one device.
The system meets the requirements of 10CFR70.24(a)(2).
The system is tested quarterly by exposing the detectors to appropriate sources and sounding the alarm. The alarm system is designed so that the alarm continues to sound until manually reset.
The alarm is clearly audible in all portions where radiation exposure may result from an accidental criticality incident.
If the system for a facility does not have emergency backup power, all movements of SNM are suspended during a power failure.
6.5.5.4 Laboratory Equipment Laboratory counting equipment is listed in Table 6-1.
Procedures are in place to use this equipment to determine the radioactivity in such things as: basin water samples, process water samples, environmental samples, air samples, stack gas samples, smears, etc.
o 7-1 3/87 7.0 MAINTENANCE OF RADIOIDGICAL CONTINGENCY PREPAREDNESS CAPABILITY 7.1 Written Procedures The responsibilities for preparing implementing procedures-and reviewing procedure effectiveness are assigned in Vallecitos Safety Standard 1.4,
" Emergency Preparedness and Response".
Each implementing procedure will be reviewed, evaluated and approved by the appropriate individuals.
Review shall be obtained from all organizational functions identified within the procedure.
Changes to the procedures will be in accord with NS Administrative Procedure No. 150, " Document Control". Manager, Nuclear Safety, shall approve all proposed changes and determine whether additional review and approval are needed.
Paragraph 7.4 establishes an annual review cycle for the radiological l
contingency plan.
7.2 Trainine Emergency procedures, no matter how well written, are effective only if the persons who are to respond to them and who implement them are familiar with their contents and have the capability of following them.
Consequently, training is one of the most important aspects of any emergency preparedness program.
This section is intended to specify who the emergency response personnel are and to describe the training that is provided to the emergency staff and off-site support eersonnel.
7.2.1 Emercency Trainine Program Emergency preparedness training (except fire fighting), reviews, and coordination of tests, drills, and critiques are provided by the Nuclear Safety function; but the responsibility for assuring facility specific personnel are trained rests with the Area Manager (s) for the facility.
Fire fighting training is provided by the Site Fire Marshal. Assigned emergency response personnel are given the appropriate radiological safety training courses as well as specific training related to their particular team or functional assignments. Off-site support personnel are invited to participate in these training sessions; and tours can be arranged to familiarize them with the topographical layout, site facilities, types of work performed, and the materials handled at the VNC site.
The following courses are given as appropriate for the facilities, activities, and materials at risk at VNC to provide the necessary degree of training as part of the required emergency preparednass program.
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7-2 3/87-
.1.
New Emolovees Radioloeical' Safety Orientation (NERSO) is a course which provides an introduction to the. knowledge required-to work. safely in the areas found at the VNC site. Course' contents; include.the" general plant layout, 10CFR19, require'ments, radiation dose limits, radiation warning.
signs, criticality and high. radiation' alarms, personnel dosimetry basic.
health physics instrumentation operation,. basic atomic physics,.and a-brief introduction tolthe biological effects of: radiation exposure.
~
2.
Radiological Safety At Vallecitos Nuclear Center'(RSVNC) is the main training course for imparting radiological safety information.to i
-employees. This courseLis generally intended for employees and visitors I
who have' unescorted, uncontrolled access to Posted Radiation Areas at VNC. All topics covered in the NERSO: course are covered in much more depth in this course.~ The trainee is trained.to a degree at which, with
~
on-the-job experience, he should be a fully. competent radiation worker from.the radiological safety perspective.
3.
Resoiratory' Protection Training Course (RPTC) is'given to'all VNC.
g indiation workers who may need to wear respirators as part of their work.
-l Emergency tear; members who might' have to enter airborne radioactivity.
areas or confined spaces are trained and fit tested with self-contained l
breathing apparatus. Training is provided on the proper use and' care of respiratory protective equipment,' including emergency actions for equipment malfunction.
4.
Criticality Safety Trainine (CST) is provided to all'. radiation workers l
who may work.without direct supervision with fissile materials. An introduction to this subject is made in the NERSO course and is reinforced in the RSVNC course; but in-depth and sometimes facility specific criticality safety is taught in_the CST. course..Precautioaary ar.d preventive topics on criticality safety are taught, as well as'a
" hindsight review" of previous criticality accidents.
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5.
Fire'and D===ne Control Trainina (FDCT).
This' course is directed toward) l T
Building Emergency. Team firemen and selected plant maintenance personnel.
The training includes operation of installed fire protection systems,<
portable fire extinguishers, life' support systems;;and techniques i
employed to limit the damage caused by an accident, i
.]
.6.
Emernency First Aid and Rescue Trainine (FARED). First aid designates for the_ building emer6ency teams will participate in this course. crhe l
training meets the. standards established by.the American' Red Cross and covers basic first aid, cardiopulmonary resuscitation-(CPR), rescue techniques, and emergency dose-limits.
7.
Radiation Safety Technician Certification Course (RSTCC). -The course'is l.
intended to complement on-the-job monitoring training for healthL physics technicians. The initial sections of the~ course deal with basic information concerning atomic structure and' physical. quantities; natural -
radioactivity; properties of alpha, beta, gamma, X-rays,' and neutrons;-
radiation units and external dose determinations; and shielding.
Biological effects of radiation are noted, followed by discussions of background radiation, radiation protection standards, and internal. dose calculations.
The remaining sections cover topics dealing with certain aspects of~
radiation monitoring:
radiation detection principles; instrument-operation and counting' statistics; health ~ physics instruments and personnel monitoring ~ devices; and the nature of, principles of; operation of, and monitoring approachesoto air sampling, reactors,_ hot cells, and accelerators.
., s 7-5 3/87 7.3 Tests and Drills Periodically, on-site emergency drills will be conducted to test the adequacy of emergency plans and procedures.
The drills will be planned and performed to specifically test the following:
(1) System for notification of on-site personnel.
(2) Prompt and effective evacuation of the involved facility or area.
(3) Performance of the on-site emergency organization.
(4) Avnilability of emergency equipment.
(5) System for notification of off-site personnel and organizat. ions.
At least annually, drills will be held to test the integrated response of the on-site emergency control organization to (1) simulated fire in each of the primary areas or facilities at VNC, and (2) simulated criticality in each facility that has a potential for an accidental criticality accident.
At least every two years, drills will be performed to test the system for notification of off-site personnel and organizations.
A critique will be held for each drill performed. Lessons learned and pertinent observations will be identified and reported to management for evaluation.
If appropriate, changes to emergency plans and procedures will be made.
7.4 Review and Uodating of the Plan and Procedures The Manager, IP, is responsible for:
l 1
1.
Preparing and instituting an emergency plan.
2.
Periodically reviewing the plan's effectiveness.
3.
Reviewing the plan for potential modification annually.
The Manager, IP, has assigned the responsibility for coordination of these activities to the Manager, NS.
Responsibility for maintenance of specific portions of the plan is assigned to appropriate organizational components.
Area Managers are responsible for developing and maintaining appropriate implementing procedures. The site plan will be reviewed annually and the implementing procedures biennially and whenever there are significant changes in processes, kinds of material or inventory at risk, and plant organization,
,. s 7-6 3/87 7.5 Maintenance and Inventory of Radiolonical Emercency Eauipment. Instrumentation. and Sunolies 7.5.1 Maintenance Responsibility Activities involving radioactive materials are performed in a number of buildings at VNC located far enough apart that it is extremely unlikely all areas would be affected by one radiological incident. As a result, it is usually assumed in the emergency plans that equipment and suppliet will be available from the unaffected areas on site.
Operational readiness of much of the equipment such as radiation detection instruments, radios and alarm systems is assured by their daily use for routine operations; and the testing and maintenance are part of a routine preventive maintenances program.
Responsibility for the maintenance of equipment and supplies that are for use during an emergency has been assigned to various organizations.
The Manager, Reactor Operations & Support Services (RO&SS), has the following responsibilities:
1.
Installation, maintenance, and modification of the emergency facilities and equipment that have site-wide application, e.g.,
emergency communications systems, criticality alarm system, site
/
dlarm system, fire-fighting equipment, and emergency power and lighting systems.
2.
Maintenance, including calibration, of instrumentation used for the radiation protection of personnel.
3.
Maintenance of the respiratory protection equipment authorized for emergency use, i.e., the SCBA equipment.*
4.
Establish test procedures and periodically test the operational readiness of the emergency equipment listed in the preceding paragraphs.
The Manager, Nuclear Safety, is responsible for the following:
1.
Review of operating components to assure that all portable survey instruments are forwarded to the instrument shop when calibration or maintenance is required.
2.
Routine inspection of radiological emergency supply cabinets and I
replenishment of equipment and supplies as necessary.
- Responsibility temporarily assigned to Manager, Remote Handling Operation.
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so 7-7 3/87 The Occupational Health Nurse is responsible for maintaining the emergency l
medical supplies.
In addition to the preceding specific assignments, it is the responsibility of Area Managers to maintain in operational readiness the equipment required to implement the site emergency plans and impleuenting procedures for their area (s) cf responsibility.
7.5.2 Calibration and Maintenance Procedures Routine calibrations of radiation survey instruments are performed as follows:
a.
Alpha calibrations by use of commercially available scurces, b.
Beta calibrations by use of a slab of natural uranium in radioactive equilibrium with Th-234 and Pa-234.
c.
Neutron instrument calibrations are performed by measuring respons.
to a pulse generator and an Am-Be neutron source.
d.
Gamma calibrations using a Cobalt-60 source standardized with a meter. The calibration of the meter is traceable to the NBS.
All radiation monitoring instruments are calibrated as frequently as deemed necessary to assure reliability during use.
Pottable: radiation monitoring instruments are calibrated as required by License SNM 960.
Stack particulate monitor systems are calibrated by placing a uniformly distributed radioactive source in the same geomet.ry as the filter paper used for collecting particulates. Stack gas monitor systeins are checked routinely by placing a reference gamma source near the detectors and observing whether the response falle within prescribed limits. Calibration with a known radiogas standard has been performed to verify this procedure.
Iodine monitors also are source check'd routinely.
e With the exception of the inspection, survey, decontamination and sanitization of routine-ase respirators, all inspection, testing, servicing, and repair of respiratory protective equipment at the VNC site are performed only by, or under the direct supervision of, maintenance personnel having extensive experience in the use and maintenance of such equipment.
Additionally, all such maintenance work on SCBA equipment is performed only by personnel who have received special training in SCBA maintenance by the m3nufacturer of the specific type of SCBA being worked on and who have been so certified by the manufacturer.
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