ML20214P665
| ML20214P665 | |
| Person / Time | |
|---|---|
| Site: | Battelle Memorial Institute, 07000008 |
| Issue date: | 07/19/1976 |
| From: | Lear G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214P605 | List: |
| References | |
| R-004-A-013, R-4-A-13, NUDOCS 8706030482 | |
| Download: ML20214P665 (18) | |
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'g NUCLEAR REGULATORY COMMISSION j
UNITED STATES
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WASHINGTt N, D. C. 20555 i
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UNITED STATES NUCLEAR REGULATORY COMMISSION BATTELLE MEMORIAL INSTITUTE DOCKET NO. 50-6 AMENDMENT TO FACILITY LICENSE s
Amendment No. 13 License No. R-4 1.'
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Battelle Memorial Institute (the licensee) dated March 4, 1976, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Conunission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; and
'. The issuance of this amendment will not be inimical to the common D
defense and security or to the health and safety of the public.
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
F.
Publication of notice of this amendment is not required since it does not involve a significant hazards consideration nor amendment of a license of the type described in 10 CFR Section 2.106(a)(2).
8706030482 870514 PDR ADOCK 07000006 p
2.
Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment.
j 3.
This license amendment is effective as of the date of its issuance.
FOR Tile NUCLEAR REGULATORY COMMISSION George ear, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications
, Date of Issuance:
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ATTACHMENT TO LICENSE AMENDMENT NO. 13 TO THE TECHNICAL SPECIFICATIONS FACILITY OPERATING LICENSE NO. R-4 DOCKET NO. 50-6 Replace in its entirety the Technical Specifications with the attached revised pages.
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r TABLE OF CONTENTS Page 1.0 DEFINITIONS.
. 1-1
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1-1 l
1.1 Reportable Occurrence 1.2 Channel Check
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. 1-1 1.3 Chennel Calibration
. 1-1 I
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1.4 Channel Test.
. 1-1 e-N-1.5 Measured value.
. 1-2 1.6 Measuring Channel
. 1-2 1.7 Operable.
. 1-2 1.8 Operating
. 1-2 1.9 True Value.
1-2 2.0 LIMITING CONDITIONS FOR POSSESSION ONLY.
. 2-1 2.1 Water Monitoring.........
2-1 3.0 SURVEILLANCE REQUIREMENTS.
. 3-1 3.1 Water Monitor
. 3-1 3.2 Dismantled Facility 3-2 4.0 DESIGN FEATURES.
4-1 4.1 Site Description.
. 4-1 4.2 Retired Facility.
. 4-1 5.0 ADMINISTRATIVE CONTROLS.
. 5-1 5.1 Organiz.ation.
5-1 L/
5.2 Review and Audit.
. 5-1 5.3 Action to be Taken in the Event of a Reportable
'l Occurrence.
. 5-6 5.4 Records
.'5-7 5.5 Reporting Requirements.
. 5-7 5.5.1 Annual Repcrts
. 5-8 5.5.2 Non-Routine Reports -- Reportable Occurrence Report.
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i Amendment No. 13
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"1.0
' DEFINITIONS _
i 1.1 REPORTABLE OCCURRENCE. Reportable Occurrence is any of the following:
A measuring system setting less conservative than the limiting a.
1 setting established in the Technical Specifications, b.
Any unplanned or uncontrolled release of radioactive material from the facility.
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c.
An observed inadequacy in the implementation of administrative or procedural controls such that the inadequacy causes or threatens to cause the existence or development of an unsafe condition in connection with the possession of the retired facility.
d.
The entrance of an unauthorized person or persons into the facility,
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A significant change in the radiation or contamination levels in the facility or the offsite environment.
1.2 CHANNEL CHECK.
A' channel check is a qualitative verification of acceptable performance by observation of channel behavior. This verification shall include comparison of the channel with other independent channels or systems that measure the same variable.
1.3 CHANNEL CALIBRATION. A channel calibration is an adjustment of the channel such that its output corresponds with acceptable accuracy to known values of the parameter that the channel measures.
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Calibration shall encompass the entire channel, which ' includes equipment actuation, alarm, or trip and shall be deemed to include the Channel Test, as defined below.
1.4 CHANNEL TEST. A channel test is the introduction of a signal into the channel to verify that it is operating.
Amendment No. 13
r 1-2 1.5 NIASURED VALUE. The measured value of a process variable is the value of the variable as registered by a properly calibrated measuring I
channel.
1.6 HEASURING CHANNEL. A measuring channel is the combination of sensors, amplifiers, and output devices used for measuring'the value of a process variable.
1.7 OPERABLE. A component or system is defined as operable if it is capable of performing its intended function in a normal manner.
- 1. 8 OPERATING. A component or system is defined as operating if it is performing its intended function in a normal manner.
1.9 TRUE VALUE. The true value of a parameter is its theoretically correct value at any instant.
Amendment.No. 13
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2.0 LIMITII<G CONDITIONS FOR POSSESSION ONLY,
2.1 WATER MONITORTNG Applicability This specification applies to monitoring water pumped from the, sump of the retired facility af ter dismantling is complete.
Ob iective To ensure that radioactivity levels in water pumped from the, sump in the retired facility do not exceed 10 CFR 20 limits.
Specifications a
Discharge of water from the sump shall not be continued if the gross activity level exeeds the limit specified in 10 CFR Part 20.
Bases The water monitor is utilized to monitor the water pumped from.the sump at the lowest point in the retired facility.
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Amendment No. 13 M
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1 3.0 SURVEILLANCE REQUIRDENTS 3.1 WATER MONITOR Applicability This specification applies to surveillance requirements for dhe water monitor.
Obiectice To ensure that the water monitor is operable as required ~in Specification 2.1.
I specification The water monitor shall be calibrated annually at periods not to exceed 14 months, and a channel test shall be performed each month.
Bases I
Periodic tests of the water monitor will ensure its operability; annual l
calibration will detect Any long-term drift that is not detected by routine tests of the c,hannel.
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3 -2 32 DISMANTLED FACILITY Applicability This specification applies to the surveillance of the retired facility after dismantling is complete.
Obiective To ensure that the remaining radioactivity remains in place and to prevent inadvertent exposure to radiation areas above 5 mR/hr.
Specification A facility radiation survey shall be performed' quarterly at intervals,
a.
not to exceed 4 months.
b.
An environmental radiation survey shall be performed semiannually at intervals not to exceed 8 months.
c.
The physical barriers shall be inspected quarterly at intervals not to exceed 4 months.
Bases The quarterly radiation survey will varify that no radioactive material is escaping or being transported from the facility to the environs.
The semiannual environmental survey will confirm that no significant amounts of radiation have been released from the facility.
The i
quarterly check of the physical barriers will ensure that these barriers have not deteriorated and that locks and locking apparatus are intact.
Amendment No. 13
4-1 4.0 DESIGN FEATURES 4.1-SITE DESCRIPTION i
The retired facility is located at the Battelle Nuclear Science Area which is part of the 1000-acre tract of land owned by Battelle Memorial Institute.
The site is located approximately 15 miles west of downtown Columbus, Ohio.
The minimum distance of the reactor building to the exclusion fence is about 1175 feet.
The Nuclear Science Area, which consists of the Hot Laboratory, Critical Assembly Laboratory, the Plutonium Facility and Battelle Research Reactor, is surrounded by an 8-foot-high chain-link security fence with three-strand barbed wire at the top.
The closest proximity of this fence to the retired facility is about 100 feet.
Access to the Nuclear Science Area is limited to authorized personnel on the Site Access L'ist or visitors accompanied by an authorized person.
This list is maintained in compliance with the Site Security Plan.
4.2 RETIRED FACILITY The retired facility is located in a building which is shockproof, fire-proof, and relatively gas tight.
The building is 131 feet long, 66 feet wide and is about 44 feet above ground.
The building is constructied of cement block faced with brick up to 24 feet above ground and aluminum Q-mecal siding the rest of the way.
Partial floors at the second-and third-floor level are supported by the reactor shield and building walls. The first. floor level is 12 ft below ground level. The building is serviced by an overhenck 10-ton crane and a drive-in truck port.
Amendment N,o. 13 m
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5.0 ADM$NTSTRATIVE CONTROLS 5.1 GRGANIZATION 5.1.1 The organizational structure of Battelle's Columbus Laboratories related to administration of the retired facil'ity shall be as shown in Figure 5.1.
.s 5.1.2 The retired facility shall be maintained under the following criteria:
5.1. 2.1 The Retired Facility Site Representative (RFSR) shall be responsible for controlling authorized access into and movement within the facili-ty and will also be respons'ible for compliance with 'the retired facility license.
5.1. 2.2 In all matters pertaining to compliance with the requirements of 5.1. 2.1, the RFSR shall report to and be directly responsible to k-the Section Manager or assigned Associate Section Manager.
5.1. 2. 3 The RFSR shall have knowledge of NRC requirements and the retired facility license.
5.2 REVIEW AND AUDIT 5.2'1 Operations in the retired facility shall be reviewed and audited by a comittee.
The committee shall be designated as the By-Product Subcommittee (RSC-3) of the BCL Radiological Safety Committee (RSC) and shall function under the guidance df the Laboratory Director as specified in the Radiological Safety Committee Charter and the specific guidelines given in these Technical Specifications.
Amendment No. 13
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Director Chairman Batte11e's Columbus Labs Radiological
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BCL I
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Department Manager g
Radiological y
Section Manager Sai'ety Officer Byproducts Associate Section Manager i
Subcommittee I
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Retired J
Facility i
Site Rep f
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i FIGURE 5.1.
ADMINISTRATION OF THE RETIRED FACILITY l
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Amendment No. 13 e
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e 5-3 5.2.2' The scope of the By-Product Subcommittee includes all potential hazards of handling any radioactive materials of Z 1ess than 90 but excluding products in the decay chains of elements of Z greater than or equal to 90 if unseparated.
s 5.2.3 The By-Product Subcommittee shall consist of at least four members, of whom no more than a minority shall be from the line organization shown in Figure 5.1.
The selection of member,s shall be based on the #ollowing principles:
Each technical discipline relevant to the type of hazard in a.
the province of the subcommi,ttee should be represented, b.
There.should be a Safety Office member on the ' Subcommittee.
This is normally the Radiological Safety Officer or his alternate.
Alternates for members are appointed as potential. replacements c.
only from staff having a similar technical background.
5.2.4 Changes of By-Product Subcommittee membership may be initiated by the i
Chairman of the Ey-Product Subeccmittee who sends a recommendation to the Chairman of the Radiological Safety Committee.
If this committee acts favorably on the request, it will recommend the change to l
the Laboratory Director, who if he concurs will notify the indi-viduals involved and the secretaries of the Radiological Safety l
i Committee and the By-Product Subcommittee.
Amendment No. 13 l
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5-4 5.2. 5 The subcommittee may take any of several actions on a request:
a.
It may, by unanimous vote, reject the request.
b.
It may, by one or more dissenting votes, return the request to the originator with instructions to modify it in one or more particulars.
It may, by unanimou's vote, recommend approval of the request.
c.
5.2.6 If the subcommittee recommends approval the procedure shall be as follows:
a.
The Subcommittee shall promptly forward to the Chairman or Vice Chairman of the Radiological Safety Committee a memorandum conveying th'e r,ecommendation and attach to it any document relevant to the case.
b.
The Chairman or Vice Chair =an of the Radiological Safety Committee shall review the recommendation, and if he concurs shell prepare for the Laboratory Director's signature, a memorandum addressed to the Department Manager of the Cogn.izant Section tbnager giving approval for the request, including any stipulations which may need to be imposed.
c.
The Laboratory Director, if he approves, shall sign the memor-andum and forward ic to the Department Manager.
d.
The Department bbnager shall notify the people concerned with the ma tter.
5.2.7.
The Byproducts Subec=mittee shall meet annually at intervals not to exceed 14 months for the purpose of review of the retired facility status.
Amendment No. 13
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'5.2.8 The quorum shall consist of i
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At least four members or alternate members, b.
At least one member or alterna te member fro:n eac of the technical disciplines represented on the subcommittee, includ-ing the Safety Office, p.
No member who is the, experi= enter, his section manager, the operating supervisor or his section manager, or any person who has contributed significantly to planning the experirent or will be directly concerned with its conduct.
The subcommittee may request the atter. dance of any person who can-Provide information needed for review.
'5.2.9 complete records of every Subcom$ittee action shall be maintained by the secretary of the By-Product Subcocmittee and by the secretary of the Radiolo;;ical Safety Committee.
5.2.10 The By-Product Subcommittee shail audit annually, at periods not to ex-ceed 14 months, the possession-only license of the retired facility includi-
.administra tive and operational procedure _s,_ equipment maintenance, plant-equipment performance, standard-operating-procedures, abnormal occurrences, and possession records to insure compliance with proced-ures, regulations, and license provisions including the Technical Specifications.
5.2.11 The Radiological Safety Officer is the Health Physicist appointed by the Laboratory Director to represent the Laboratory Director and the Radiological Safety Committee in matters of radiological safety.
/c.cndment No. 13 us==
I Th2 Radislegical Safsty Officar is cssign:d by the Labsrctory Diracter and ths Radiologicc1 S3faty Cemittso tha rep:nsibility to maintain an overview of all work with radioactive materials and ionizing-radiation-producing devices to assure himself that the procedures are performed within the rules and regulations of the concerned governnent agencies and the Radiological Safety Comittee.
This responsibility is carried out by Participating in meetings of the. Radiological Safety Comittee a.
and the subcommittees, b.
Auditing health physics records, Auditing routine records of the facilities working with radio-c.
active materials, d.
Observing the radiation safety activities of operations personnel, Observing the staff performance of routine and Radiological e.
Safety Committee-approved work with radioactive materials and radiation-producing machines, f.
Taking appropropriate action when performance does not comply with the facility operating procedures or regulations.
5.3 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE OCCURRENCE In the event of a reportabic occurrence, as defined in these Technical Specifications, the following action shall b'e taken:
5.3.1.
The RTSR shall be notified of the occurrence.
Corrective action shall be taken to correct the reportable conditions and to prevent its recurrence.
5.3.2.
A report of such occurrences shall be made to the By-Product Subcommittee the Chairnan of the Radiological Safety Committee and to the Amendment No. 13
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U S N R C. in cecordanca with Smetica 5.5.2.
Tha rsport
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shall include an analysis of the causes of the occurrence, the l
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effectiveness of corrective actions taken,.and the recommendations ~
of measures to prevent or reduce the probability or consequences of recurrence. The report shall be made in acco'rdance with the format contained in Appendix E of Regulatory Guide 1.16, Revision 4.
5.4 RECORDS 5.4.1 The following records and logs shall be prepared and retained by the licensee for at least 5 years:
a.
Maintenance log, b.
Dismantling log book.
5.4.2 The following records.and logs shall be prepared and retained by the licensee until the license is terminated:
a.
Caseous and liquid waste released to the environs *,
b.
Offsite environmental-monitoring surveys *,
c.
Radiation exposures for personnel *,
d.
Fuel inventories and transfers *',
e.
Facility radiation and contamination surveys, f.
Proceedings of the pertinent Subcommittee, g.
Inspection of the physical barriers to the retired facility, h.
Reportable occurrences.
5.5 REPORTING REQUIREMENTS The following information shall be submitted to the US.NRC in addition to the reports required by T[tle 10, Code of Federal i
Regula tions.
- These facility records are maintained with other BCL records of this type and are held by other BCL components in accordance with NRC regulations.
Amendment No. 13
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' 5.5.1 Annual Rsports An Annual Report covering the previous year shall be submitted to Thd 'birector, Division of 0perating Reactors, U. S. Nuclear Regulatory l
Commission, Washington, D. C. 20$55.
It shall include the following:
Results Of environmental and retired facility radiation surveys, a.
b.
Status of the facility, Evaluation of the performance of security and scrveillance c.
- measures, d.
Reportable occurrences, which includes entry of an unautherized h
person or persons and significant changes in radiation or contamination levels in the facility or off-site environment.,
5 J '.2 Non-Routine Reports -- Reportable Occurrence Report Notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of discovery of a re-portable occurrence, by telephone, and telegraph to the Inspection &
Enforcement Regional Office (ce to the Director, Division of,0perating Reactors. The Reportable Occ.urrence will also be reported in the l
Annual Report.
Amendment No. 13 l
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