ML20148K858
| ML20148K858 | |
| Person / Time | |
|---|---|
| Site: | Portsmouth Gaseous Diffusion Plant |
| Issue date: | 01/31/1997 |
| From: | External (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20148K525 | List: |
| References | |
| POEF-LMES-90, NUDOCS 9706180449 | |
| Download: ML20148K858 (22) | |
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POEF-LMES-90
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Technical Safety Requirements.
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Portsmouth Gaseous Diffusion Plant Department of Energy Nonleased Facilities Piketon, Ohio l
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9706180449 970131 PDR ADOCK 07007002 B
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O POEF-LMES-90 TECHNICAL SAFETY REOUIREMENTS i
PORTSMOUTH GASEOUS DIFFUSION PLANT, DEPARTMENT OF ENERGY NONLEASED FACILITIES Date Approved:
O Prepared by LOCKHEED MARTIN, ENERGY SYSTEMS, INC.
managing the Environmental Management Activities at Portsmouth Gaseous Diffusion Plant and Paducah Gaseous Diffusion Plant under contract DE-AC05-840R21400 and managing Oak Ridge K-25 Site and Oak Ridge Y-12 Plant O
for the U.S. DEPARTMENT OF ENERGY
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f POEF-LMES-90 REVISION LOG REVISION NUMBER DESCRIPTION RO Initial issue O
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POEF-LMES-90 TABLE OF CONTENTS Eage Section 1 Use and Application 1.0 USE AND APPLICATION............................. 1-1 1.1 DEFINITIONS..................................... 1-2 1.2 OPERATION AL MODES............................. 1-5 1.3 LIMITING CONDITIONS FOR OPERATION................ 1-6 1.4 TIME INTERVALS FOR SURVEILLANCE................. 18 1.5 SURVEILLANCE REQUIREMENTS 1-9 Section 2 Safety Limits 2.0 S A FETY LIMITS................................... 2-1 Section 3/4 Operational Limits and Surveillance Requirements O
3/4.0 OPERATIONAL LIMITS AND SURVEILLANCE REQUIREMENTS................................
3/4-1 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 5.2 ORGANIZATION.................................
5-1 5.2.1 O n-S i te..................................... 5-1 5.2.2 Facility Staff................................. 5-2 5.3 PROC ED URES.................................... 5-2 5.4 PROG RAM S...................................... 5-2 5.4.1 Nuclear Criticality Safety Program................... 5-2 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........................... 5-5 O
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O POEF-LMES-90 LIST OF ACRONYMS, ABBREVIATIONS, AND SniBOLS Isan Definition 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 LCS limiting control setting LMES Lockheed Martin Energy Systems, Inc.
NCS nuclear criticality safety PORTS Portsmouth Gaseous Diffusion Plant PSS Plant Shift Superintendent SAR safety analysis report h
SL safety limit SR surveillance requirement TSR technical safety requirement A
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Section 1 - Use and Application 1
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POEF-LMES-90 1.0 USE AND APPLICATION The Portsmouth Gaseous Diffusion Plant (PORTS) is owned by the U.S. Department of Enerr; (DOE). The production-related facilities are leased to the United States Enrien.nent 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 Emiclunent Facilities (EM&EF) activities. The facilities 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-1027-92.8 Any deviations from the generic requirements will be described in specific limiting conditions for operations (LCOs) as applicable.
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l POEF-LMES-90 1.1 DEFINITIONS Term Definition MODZ Any one fa::ihty condition specified in Sect.1.2 OPERABLE / OPERABILITY A system or component is OPERABLE when it and its support systems and components are capable of performing their intended safety funct on(s) or intended support function, i
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
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shall be immediate SAFETY LIMIT (SL)
A limit on process variables associated with those physical barriers, generally passive, that 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, REQUIREMENT (SR) or INSPECTION to ensure that the necessary OPERABILITY of systems and components is maintained or that operations are within the specified SLs, LCSs, and LCOs 1-3
POEF-LMES-90 1.2 OPERATIONAL MODES The MODES for the PORTS DOE nonleased facilities are ac follows:
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Cylinder handling / storage This mode of operation includes receipt / shipping / storage, handling, and on-site transport of all UF cylinders. This mode will address 6
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, pa*ching, stacking, cleaning, painting, and testing). In addition, this mode of operation includes any pigtail connections / disconnections Waste This mode of operation addresses the handling of handling / storage radioactive and hazardous was:es that exceed Category 3 threshold values, identified in DOE-STD-1027-92, as well as other material (e.g., lithium) and it includes activities supporting the characterization, certification, packaging, on-site transport, and storage of these wastes and other materials. This mode does not include material in UF cylinders Out of operation The facility is not performing any normal operation in this mode, and the hazardous mate;ials that exceed the Category 3 threshold values, identified in DOE-STD-1027-92, have been removed from the facility h
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POEF-LMES-90 l.3 LIMITING CONDITIONS FOR OPERATION entered permit operation in the MODE or other specified condition for only a limited time.
I.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 demonstra'.e 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
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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 i
OPERABILITY. Sect.1.3.2 is still applicable to the supported system.
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POEF-LMES-90 1.5 SURVEILLANCE REQUIREMENTS SRs are requirements relating to test, calibration, or inspection to ensure that the necessary quality of safety-re. lated 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.
For frequencies specified as "once," the above interval extension does not apply, h
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 the ACTIONS begin IMMEDIATELY on failure to meet the surveillance.
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O Section 2 - Safety Limits O
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i POEF-LMES-90 2.0 SAFETY LIMITS There are no SLs for the PORTS DOE nonleased facilities.
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O Section 3/4 - Operational Limits and Surveillance Requirements 4
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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 Conditions and ACTIONS for not meeting an LCO will be completed and submitted to DOE after USEC completes these items for NRC certification. This system is a leased system with operability requirements for both leased and nonleased facilities. Due to the shared nature of this sytem, it is highly desirable to be consistent for the entire plant.
SURVEILLANCE REQUIREMENTS SRs for this LCO will be completed and submitted to DOE after USEC completes these items for h
NRC certification. This system is a leased system with operability requirements for both leased and nonleased facilities. Due to the shared nature of this sytem, it is highly desirable to be consistent for the entire plant.
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O Section 5 - Administrative Controls a
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POEF-LMES-90 5.0 ADMINISTRATIVE CONTROLS 5.1 CONTRACTOR RESPONSIBILITY 5.1.1 The EM&EF Site Manager 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 staffin 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 at the plant and for the central control room command function. This function a shared site responsibility for leased and nonleased facilities.2 During any absence g of the PSS from the central control room while the plant is operational, an authorized designec 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 / Owner shall be responsible for the operations conducted within the facilities affected by this TSR for which he/she is responsible.
1 5.2 ORGANIZATION 5.2.1 On-Site i
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 j
EM&EF activities and are described in Sect.17.3 of the SAR.
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POEF-LMES-90 5.4 PROGRAMS CAAS coverage, procedure requirements.
l posting and labeling requirements, change control,'
a operation surveillance and assessment, and technical aspects.
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U and a700 g of 23;J shall be based upon a documented nuclear criticality safety evaluation 3
and 3. hall 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 i
be validated for the appropriate range of applicability and these validations J
shall be documented, 5.4.1.3 The double-contingency principle, as described in the SAR, shall be used as
[. Q 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 evaluated and documented exceptions must be provided to and approved by DOE.
i 5.4.1.4 The CAAS is a leased system and provides coverage for nonleased operations within leased facilities. For nonleased operations within leased facilities, the requirements for the CAAS will be in accordance with the leased facility TSRs.2 l
5.4.2 Radiation Protection Program
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A raWation 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, personnel exposure control and measur'ement, a
contamination control, a
radioactive material control, a
radiological protection instruments and equipment, and records and reports.
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POEF-LMES-90 5 4 PROGRAMS Vendor testing of ordered equipment meets requirements.
Proper equipment is received and installed.
Installed equipment satisfies specifications and demonstrates satisfactory performance.
The surveillance program shall meet the following objectives for any equipment designated as safety-class or requires an operating limit in Sects. 2,3, and 4:
identify the activities to be monitored, identify the frequency of the surveillance, e
identify the individual or organization responsible for conducting the surveillance, generate and update surveillance schedules and plans, e
assess compliance, document surveillances, and document nonconformances and initiate corrective actions.
5.4.6 Maintenance Program O
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:
- training, raaintenance procedures, maintenance programs, work control, postmaintenance testing, e
procurement, receipt inspection, control, and issuance of safety-class and safety significant items, repair parts, materials and services, control of measuring and test equipment, and maintenance history.
5.4.7 Conduct of Operations A conduct of operations program shall be established, implemented, and maintained as described in the SAR Sect.11.3. The conduct of operations program shall address the following elements:
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5.4 PROGRAMS 5.4.10 Quality Assurance Program l
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 i
and shall ensure that the following objectives are met:
Ensure that personnel are trained and qualified to perform their assigned work I
and are provided continuing training to ensure that job proficiency is maintained, l
Establish and implement processes to detect and prevent quality problems and
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to ensure quality improvement.
Prepare, review, approve, issue, use, and revise documents to prescribe processes, specify requirements, or establish design.
i Perform work to established technical standards and ADMINISTRATIVE l
- CONTROIS, Design items and processes using sound engineering / scientific principles and Q
appropriate standards.
Ensure that procured items and services meet established requirements and l
perform as specified.
Inspect and acceptance-test specified items and processes using established i
acceptance and performance criteria.
Assess, at all levels, the integrated quality assurance program and its
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performance.
Perform planned and periodic independent assessments to measure item quality and process effectiveness and to promote improvement.
5.4.11 Emergency Preparedness Program i
An emergency preparedness program shall be established, implemented, and j
maintained as described in the SAR Sect.15.3. The emergency preparedness program shall ensure that the following objectives are met:
Develop and maintain emergency planning, preparedness, and response
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capabilities, as well as effective public and interagency communications, in order to minimize the consequence to workers, the public, and the environment from incidents involving DOE operations.
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POEF-LMES-90 5.7 REVIEWS AND AUDITS A system of audits and assessments is implemented at PORTS to ensure that the health, safety, safeguards, security, and environmental programs, as described in the SAR and the 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 Contracting Office Representative. All changes to operating practices that require changes to this TSR shall be approved by DOE.
5.8 FACILITY OPERATING RECORDS In addition to the requirements of applicable regulation, records and logs shall be prepared for at ' east the following items and retained for at least the period indicated in parenthcois:
normal and emergency conditions of facility operation (5 years),
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maintenance activities relative to safety-related equipment (5 years),
equipment and component SURVEILLANCE activities required by the TSRs (life of facility),
record of reviews and audits (5 years),
occurrence reports as required by DOE Order 232.1, occurrence Reporting and e
Processing of Operations Information (5 years), and training records (5 years).
a 5.9 REPORTING REQUIREMENTS In the event of a reportable occurrence, ACTIONS shall be governed by DOE Order 232.1, Occurrence Reporting and Processing of Operations Information.
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Appendix A -
Technical Safety Requirement Bases O
POEF-LMES-90 3/4.0 OPERATIONAL LIMITS AND SURVEILLANCES 3/4.1 CRITICALITY ACCIDENT ALARM SYSTEMS (CAAS) 3/4.1.1 CAAS HASES HACKGROUND The CAAS is used to warn plant personnel of a criticality or 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 partial losses of required equipment.
APPLICABLE The ability of the CAAS to provide detection / alarm coverage of SAFETY areas covered by the CAAS is required to minimize the ANALYSIS potential on-site exposure of personnel to radiation from an accidental criticality (see applicable SAR subsections 4.4).
Areas presently requiring coverage are X-345, X-7725, g
X-7745-(R)S, and X-744 G.
LCO The alamiing 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 coverage is required in areas that have more than 700 g of FISSIONABLE MATERI AI. provided no justification for excluding alarm coverage is provided.
ACTIONS To be provided SURVEILLANCE To be provided
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