ML20148L037
| ML20148L037 | |
| Person / Time | |
|---|---|
| Site: | Paducah Gaseous Diffusion Plant |
| Issue date: | 09/24/1996 |
| From: | Angelelli T External (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20148L014 | List: |
| References | |
| KY-EM-175, NUDOCS 9706190017 | |
| Download: ML20148L037 (26) | |
Text
KY/EM-175 A
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l Technical Safety Requirements.
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Paducah' Gaseous Diffusion Plant Department of Energy Nonleased Facilities Paducah, Kentucky f
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KY/EM-175 A
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9 TechnicalSafety l
Requirements.
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Paducah Gaseous Diffusion Plant Department of Energy Nonleased Facilities
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O KY/EM-175 Technical Safety Requirements Paducah Gaseous Diffusion Plant Department of Energy Nonleased Facilities l
Paducah, Kentucky Approvals hA.bbE ela/sc GDP SAR kgrade Programkanager Dafe O
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KY/EM/175 j
f TECHNICAL SAFETY REOUIREMENTS PADUCAH GASEOUS DIFFUSION PLANT, DEPARTMENT OF ENERGY NONLEASED FACILITIES l
Date Approved:
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O Prepared by LOCKHEED MARTIN ENERGY SYSTEMS, INC.
managing the Environmental Management Activities at Paducah Gaseous Diffusion Plant and Portsmouth Gaseous Diffusion Plant under contract DE-AC05-840R21400 and managing Oak Ridge K-25 Site and Oak Ridge Y-12 Plant for the U.S. DEPARTMENT OF ENERGY
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KY/EM/175 TABLE OF CONTENTS Page Section i Use and Application 1.0 USE AND APPLICATION............................. 1-1 1.1 DEFINITIONS..................................... 1-2 1.2 OPERATIONAL MODES............................. 1-5 1.3 LIMITING CONDITIONS FOR OPERATION................ 1-6 1.4 TIME INTERVALS FOR SURVEILLANCE................. 1-8 1.5 SURVEILLANCE REQUIREMENTS 1-9 Section 2 Safety Limits 2.0 SAFETY LIMITS..................
2-1 Section 3/4 Operational Liniits and Surveillance Requirements 3/4.0 OPERATIONAL LIMITS AND SURVEILLANCE REQUIREMENTS................................
3/4-1 h 3/4.1 CRITICALITY ACCIDENT ALARM SYSTEMS............
3/4-1 Section 5 Administrative Controls 5.0 ADMINISTRATIVE CONTROLS........................ 5-1 5.1 CONTRACTOR RESPONSIBILITY 5-1 l
5.2 ORG ANIZATION.................................. 5-1 5.2.1 O n-S ite..................................... 5-1 5.2.2 Facility Staff................................. 5-2 l.
5.3 PROC ED URES.................................... 5-2 5.4 PROG RAMS.....................................
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5.4.1 Nuclear Criticality Safety Program................... 5-2 l
5.4.2 Radiation Protection Program...................... 5-3 5.4.3 Hazardous Material Protection Program................ 5-4 5.4.4 Radioactive Waste Management Program.............
5-4 5.4.5 Initial Testing and In-Service Surveillance Testing Program... 5-4 5.4.6 Maintenance Program
..........................5-5 5.4.7 Conduct of Operations........................... 5-6 5.4.8 Fire Protection Program..
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KY/EM/175 LIST OF ACRONYMS, ABBREVIATIONS, AND SYMBOLS ALARA as low as reasonably achievable ANS American Nuclear Society ANSI American National Standards Institute CAAS criticality accident alarm system DOE U.S. Department of Energy EM&EF Environmental Management and Enrichment Facilities IFSM Installation Facility Safety Manager LCO limiting condition for operation 1
LCS limiting control setting LMES Lockheed Martin Energy Systems, Inc.
NCS nuclear criticality safety PGDP-Paducah Gaseous Diffusion Plant PSS Plant Shift Superinteraient SAR safety analysis report SL safety limit i
O sa surveiti>acere9uire= eat TSR technical safety requirement 3
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Section 1 - Use and Application l
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O KY/EM/175 1.0 USE AND APPLICATION
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The Paducah Gaseous Diffusion Plant (PGDP) is owned by the U.S. Department of Energy (DOE).
The production-related facilities are leased to the United States Enrichment Corporation for producing enriched uranium. The remaining facilities are retained by DOE as nonleased facilities and are managed by Lockheed Martin Energy Systems, Inc. (LMES).
These facilities currently house various Environmental Management and Enrichment Facilities (EM&EF) activities. The requirements covered by this technical safety requirement (TSR) document are generic in nature and are applicable to all facilities that exceed the Category 3 threshold values identified in DOE-STD-1027-92.2 Any deviations from the generic requirements will be described in specific limiting conditions for operations (LCOs) as applicable.
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1.1 DEFINITIONS i
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Term Definition i
OPERABLE / OPERABILITY A system or component is OPERABLE when it
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and its support systems and components are capable of performing their intended safety function (s) or intended support function, respectively.
A system or component is considered OPERABLE when the required SURVEILLANCE has been accomplished in accordance with the required frequency and there is no indication of inoperability. When a system or component is determined to be incapable of performing its intended safety function (s), the declaration of inoperability shall be immediate SAFETY LIMIT (SL)
A limit on process variables associated with those physical barriers, generally passive, that g
i are necessary for the intended facility function and that are required to guard against the uncontrolled release of radioactivity and other hazardous materials. Process variables subject to SLs are measurable parameters that, individually or in combination, reflect the basic hazard for which controls or limits are specified SURVEILLANCE A requirement relating to testing, calibration, or REQUIREMENT (SR)
INSPECTION to ensure that the necessary OPERABILITY of systems and components is maintained or that operations are within the specified SLs, LCSs, and LCOs h
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O KY/EM/175 1.2 OPERATIONAL MODES The MODES.for the PGDP DOE nonleased facilities are as follows:
Cylinder handling / storage This mode of operation includes receipt / shipping / storage,
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handling, and on-site transport of all UF cylinders. This 6
mode will address all aspects of cylinder movement, including storage, shipping, overpacking, and cylinder handling. Also included in this mode are any operations associated with the cylinders (e.g., valve changeouts, gas-over solid sampling, patching, stacking, cleaning, t
painting, and testing).
In addition, this mode of operation also includes any pigtail connections /
disconnections Waste handling / storage This mode of operation addresses the handling of radioactive and hazardous wastes that exceed Category 3
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threshold values, identified in DOE-STD-1027-92, and it
.O includes activities supporting the characterization, certification, packaging, on-site transport, and storage of these wastes. This mode does not include material in UF cylinders 6
Out of operation The facility is not performing any normal operation in this mode, and the hazardous materials that exceed the Category 3 threshold values, identified in DOE-STD-1027-92, have been removed from the facility O
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KY/EM/175 1.3 LIMITING CONDITIONS FOR OPERATION entered pennit operation in the MODE or other specified cordition for only a limited time.
1.3.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to Sect.1.3.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.
1.3.6 When a support system is inoperable and an LCO for that support system is specified in the TSRs, the supported system is not required to be declared inoperable due solely to support system inoperability. Only the support system's ACTIONS are required to be entered. This is a clarification of the definition of OPERABILITY. Sect.1.3.2 is still applicable to the supported system.
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b KY/EM/175 1.5 SURVEILLANCE REQUIREMENTS SRs are requirements relating to test, calibration, or inspection to ensure that the necessary quality of safety-reJated stmetures, systems, and components is maintained and that the LCO will be met. Sects.1.5.1 through 1.5.4 establish the general requirements applicable to all SRs and apply at all times, unless otherwise stated.
1.5.1 SRs shall be met during the MODES or other specified conditions in the applicability for individual LCOs unless otherwise stated in the SR. Failure to meet a surveillance shall constitute failure to meet the LCO (see Sect.1.3.2).
Failure to perform a surveillance within the specified frequency shall constitute failure to meet the LCO, except as provided in Sect.1.5.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.
1.5.2 The specified frequency for each SR is met if the surveillance is performed within 1.25 times the interval specified in the frequency, as measured from the previous performance or as measured from the time a specified condition of the frequency is met.
O For frequencies specified as "once," the above interval extension does not apply.
If a completion time requires periodic performance of "once every...," the above frequency extension applies to each performance after the initial performance.
Exceptions to this section are stated in the intervals described in Sect.1.4.
1.5.3 If it is discovered that a surveillance was not performed within its specified frequency, compliance with the requirement to declare the LCO not met may be delayed from the time of discovery up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified frequency, whichever is less. This delay period is permitted to allow performance of the surveillance.
If the surveillance is not performed within the delay period, the LCO shall IMMEDIATELY be declared not met, and the applicable ACTIONS shall be entered. The completion times of the ACTIONS begin IMMEDIATELY on expiration of the delay period. When the surveillance is performed within the delay period and the surveillance is not met, the LCO shall IMMEDIATELY be declared not met, and the applicable ACTIONS shall be entered. The completion times of j
the ACTIONS begin IMMEDIATELY on failure to meet the surveillance.
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Section 2 - Safety Limits O
O KY/EM/175 2.0 SAFETY LIMITS There are no SLs for the PGDP DOE nonleased facilities.
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Section 3/4 - Operational Limits and Surveillance Requirements O
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KY/EM/175 3/4.0 OPERATIONAL LIMITS AND SURVEILLANCE REQUIREMENTS 3/4.1 CRITICALITY ACCIDENT ALARM SYSTEMS LCO 3.1.1:
Nonleased processes that contain greater than 700 g of FISSIONABLE '
MATERIAL shall have operable criticality accident detection / alarm coverage capability, except where approved exemptions have been identified.
APPLICABILITY:
MODES: Waste handling / storage ACTIONS Completion Condition Required action time A.
Areas, equipment, or 1.a Discontinue movement of containers containing any IMMEDIATELY processes not covered FISSIONABLE MATERIAL.
by criticality accident M
detection / alarm Waste containing any FISSIONABLE MATERIAL Q
capability shall not be transported.
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1.b Evacuate area in which a criticality accident occurring IMMEDIATELY within the area not covered by detection capability could result in a maximum foreseeable dose exceeding 12 rad.
M Restrict access to the evacuated area.
2 IMMEDIATELY 1.c Provide personnel in the area who would be restricted under ACTION A.I.b with an alternate means nf criticality alarm notification: a device that will alarm on sensing a 20-mrad /h dose rate.
M 2.a Restore at least one fixed cluster / alarm providing 24 h detection capability and alarm capability for those areas, equipment, or processes applicable to this LCO.
2 2.b Install portable criticality accident alarm system 24 h (CAAS) unit providing required detection capability and local alarm capabilities.
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ACTION condition A 1.
Continue required ACTIONS for condition A.
IMMEDIATELY not satisfactorily M
completed 2.
Restore criticality accident detection and alarm 30 days capability to operable status.
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O Section 5 - Administrative Controls O
O KY/EM/175 5.0 ADMINISTRATIVE CONTROLS 5.1 CONTRACTOR RESPONSIBILITY 5.1.1 The EM&EF Site M'anager shall have corporate responsibility for overall safety within DOE nonleased facilities and shall have authority to take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to secure nuclear safety.
5.1.2 The Installation Facility Safety Manager (IFSM) serves as the site subject matter expert for the technical areas associated with facility safety and coordinates and oversees implementation of the Facility Safety Program for the site. The IFSM or his/her designee shall approve, prior to implementation, each proposed test, experiment, or modification to systems or equipment that affect nuclear safety.
The IFSM shall delegate in writing the succession to this responsibility when absent from the plant site.
5.1.3 The Plant Shift Superintendent (PSS) shall be responsible for emergency response Q
at the plant and for the central control room command function. This function is a shared site responsibility for leased and nonleased facilities.2 During any absence of the PSS from the central control room while the plant is operational, an authorized designee shall be named and be present in the central control room. The term " designee" means a person who has been trained to execute plant emergency procedures. The designee shall have the capability to be in contact with the PSS by using the plant communication systems when the PSS is absent from the central control facility.
5.1.4 The Facility Manager /0wner shall be responsible for the operations conducted within the facilities affected by this TSR for which he/she is responsible.
5.2 ORGANIZATION 5.2.1 On-Site On-site organizations shall be established for facility operation. The on-site organizations shall include the positions for activities affecting the nuclear safety of the EM&EF activities and are described in Sect.17.3 of the SAR.
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5.4 PROGRAMS j
CAAS coverage, procedure requirements, e
posting and labelipg requirements,
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change control, e
operation surveillance and assessment, and l
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5.4.1.1 All operations involving uranium enriched to 21.0 wt % 235U and 2700 g of U shall be based upon a documented nuclear criticality safety evaluation and l
235 shall be performed in accordance with a documented nuclear criticality safety approval.
5.4.1.2 NCS calculations shall be performed in accordance with the requirements of l
ANSI /ANS-8.1-1983. The system and codes used for these calculations shall l
4 be validated for the appropriate range of applicability and these validations shall be documented.
5.4.1.3 The double-contingency principle, as described in the SAR, shall be used as the basis for the design and operation of processes using fissionable materials. In $
each instance wherein double contingency is not met, in addition to those cases already described in Chap. 6 of the SAR, technically evahmted and documented l
exceptions must be provided to and approved by DOE.
5.4.1.4 The CAAS is a leased system that provides coverage for nonleased areas as well as nonleased operations within leased facilities. For nonleased operations l
l within leased areas, the requirements for the CAAS will be in accordance with the leased facility TSRs.2 l
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5.4.2 Radiation Protection Program A radiation protection program shall be established, implemented, and maintained as described in the SAR Sect. 7.3 and shall address the following elements:
health physics technician training and qualifications, a
personnel exposure control and measurement, contamination control, radioactive material control, a
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O KY/EM/175 5.4 PROGRAMS program shall ensure that the following objectives are met for any equipment designated as safety-class:
vendor testing of' ordered equipment meets requirements, proper equipment is received and installed, and a
installed equipment satisfies specifications and demonstrates satisfactory performance.
The surveillance program shall meet the following objectives for any equipment designated as safety-class or that requires an operating limit in Sects. 2, 3, and 4:
identify the activities to be monitored, identify the frequency of the surveillance, a
identify the individual or organization responsible for conducting the surveillance, generate and update surveillance schedules and plans, a
assess compliance,
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document surveillances, and document nonconformances and initiate corrective actions.
5.4.6 Maintenance Program A maintenance program shall be established, implemented, and maintained as described in the SAR Sect.10.5 and shall address the following program elements for any equipment designated as safety-class or safety-significant:
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maintenance procedures,
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maintenance programs, a
work control, a
postmaintenance testing, a
procurement, receipt inspection, control, and issuance of safety-class and a
i safety-significant items, repair parts, materials and services, control of measuring and test equipment, and a
maintenance history._
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systematic analysis of jobs to be performed, 1
learning objectives derived from the analysis that describe desired performance
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after training,
. training design and implementation based on the learning objectives, evaluation of trainee mastery of the objectives during training, and evaluation and revision of the training based on the performance of trained a
personnel in the job setting.
5.4.10 Quality Assurance Program A quality assurance program shall be established, implemented, and maintained as described in the SAR Sect.14.2. The quality assurance program is applicable to all facilities that exceed the Category 3 threshold values identified in DOE-STD-1027-92 and shall ensure that the following objectives are met:
ensure that personnel are trained and qualified to perform their assigned work a
and, are provided continuing training to ensure that jeo proficiency is maintained, establish and implement processas to detect and prevent quality problems and $
a to ensure quality improvement, prepare, review, approve, issue, use, and revise documents to prescribe a
processes, specify requirements, or establish design, perform work to established technical standards and ADMINISTRATIVE
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- CONTROLS, design items and processes using sound engineering / scientific principles and a
appropriate standards, ensure that procured items and services meet established requirements and a
perform as specified, inspect and acceptance-test specified items and processes usirig established acceptance and performance criteria,'
assess, at all levels, the integrated quality assurance program and its performance, and perform planned and periodic independent assessments to measure item quality and process effectiveness and to promote improvement.
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pd KY/EM/175 3_/4.0 BASES - OPERATIONAL LIMITS AND SURVEILLANCES 3/4.1 CRITICALITY ACCIDENT ALARM SYSTEMS (CAAS) 3/4.1.1 CAAS BASES f
BACKGROUND The CAAS is used to warn plant personnel of a criticality or i
radiation accident. This system is designed to detect radiation and provide a distinctive, audible signal that will alert personnel to move from those work areas which are potentially affected. The design of the system, three detector modules per cluster, provides protection for criticality events even with j
partial losses of required equipment. The CAAS also provides detection coverage in most areas by using an overlapping pattern ofindividual cluster units.
2 APPLICABLE The ability of the CAAS to provide detection / alarm coverage of Q
SAFETY' areas covered by the CAAS is required to minimize the j
ANALYSIS potential on-site exposure of personnel to radiation from an accidental criticality (see applicable SAR subsections 4.4). The only nonleased process presently requiring coverage is C-746-Q.
LCO The alarming of a criticality accident is necessary for the prompt evacuation of personnel from the affected area to a designated assembly point a safe distance from the incident.
The intent of these requirements is to ensure that adequate detection and alarm capability are provided by the CAAS to detect criticality events in any EM&EF area that could have an accidental criticality.
APPLICABILITY CAAS caverage is required in areas that have more than 700 g of FISSIONABLE MATERIAL, provided nojustification for excluding alarm coverage is provided.
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3/4.1 CRITICALITY ACCIDENT ALARM SYSTEMS (CAAS)
BASES (cont'd)
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l REFERENCES
- 1. " Criticality Accident Alarm System," ANSI /ANS-8.3, 1986.
- 2. " Request for Exemption to the Paducah Gaseous Diffusion Plant's Criticality Accident Alarm System," letter from D.
l J. Bostock to D. R. Allen November 29,1990.
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KY/EM/175 5.6 TECHNICAL SAFETY REQUIREMENTS BASIS CONTROL a change.to the way that OPERABILITY or the TSR could be met, applied, or interpreted.
Proposed changes meeting any of the above criteria shall be reviewed and approved by the DOE prior to implementation. Changes to the TSR bases that may be implemented without prior DOE approval will be provided to the DOE at least ANNUALLY.
5.7 REVIEWS AND AUDITS
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A system of audits and assessments is implemented at PGDP to ensure that the health, safety, safeguards, security, and environmental programs, as described in the SAR and the a
accompanying programs, plans, and other documents, are adequate and are effectively implemented.
This TSR shall be reviewed ANNUALLY and a report of this review forwarded to the Q
Contracting Office Representative. All changes to operating practices that require changes to this TSR shall be approved by DOE.
5.8 FACILITY OPERATING RECORDS i
In addition to the requirements of applicable regulation, records and logs shall be prepared for at least the following items and retained for at least the period indicated in parenthesis:
normal and emergency conditions of facility operation (5 years),
a maintenance activities relative to safety-related equipment (5 years),
a equipment and component SURVEILLANCE activities required by the TSRs (life e
of facility),
record of reviews and audits (5 years),
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i Appendix A -
Technical Safety Requirement Bases 4
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