ML20082T996

Forwards Revised Proposed Changes to Tech Specs for Afrri Facility License R-84

ML20082T996
Person / Time
Site:	Armed Forces Radiobiology Research Institute
Issue date:	09/10/1991
From:	Bumgarner R DEFENSE, DEPT. OF, DEFENSE NUCLEAR AGENCY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20082T998	List: ML20082T996 ML20082U000
References
NUDOCS 9109190229
Download: ML20082T996 (10)

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- DEFENSE NUCLEAR AGENCY-ARMED FORCES RADl0 BIOLOGY RESEARCH INSTITUTE

@. . BETHEcDA. M ARYLAND 20814 6145 RSDR 10 September 1991 ,

SUBJECT:

Revised Proposed Changes to Technical Specifications for AFRRI Facility License No. R-84.

Document Control Desk U.S. Nuclear Regulatory Commission

- Washington, D.C. 20555 Gentlemen: 1 The Armed Forces Radichiology Research Institute (AFRRI) reactor staff has updated our request .i for changes to the technical specifications for AFRRI facility license R-84. Please find enclosed  ;

a summary of proposed changes with safety analyses where required and complete replacement pages. All changes to technical' specifications are marked in the margins of the proposed replacement pages. ' If you have any questions or comments, please contact the Reactor Facility -

Director, Mr. Mark Moore, or the Reactor Operations Supervisor, Capt. Matt Forsbacka, at (301)-295-1290. :Thank you for your cooperation.

Sincerely, l

,k grp+ .;

ROBERT L. BUM A NER Captain, MC, USN Director

Enclosures:

as stated ,

cc: USNRC .- Region I - Project Engineer Division of Reactor Projects USNRC --Headquarters - Project Engineer Nuclear Reactor Regulation Ti 9109190229 910910 i PDR ADOCK 05000170 P- PDR I

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ATTACHMENT I REVISED PROPOSED CFIANGES TO TECHNICAL SPECIFICATIONS

- ARMED FORCES RAD 10 BIOLOGY RESEARCll INSTITUTE l

l Armed Forces Radiobiology Research Institute Bethedsa, MD 20814-5145 September 1991 l

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= 1, Page i. Tabic _oLContentL_Section 1.25: Change from " PAD" tu " ROD" to correct typographical error.

Safety Analysis: This is an administrative change to correct spelling. There are no safety implications.

2. Pagc_.L_.Section 1.9: Replace the definition for a fuel element in its entirety to

-accommodate fuel follower control rods as follows:

1.9 FUEL EllIMENT A fuel element is a single TRIGA fuel rod, or the fuel portion of a fuel follower control rod.

Safety Analysis: See previously submitted safety analysis on FFCR.

3. Page 7. Section_3JJ: Replace the second sentence of the Specifications with the following:

The normal steady state operating power limit of the reactor should be 't.0 megawatt.

Safety Analysis: See letter submitted to USNRC on August 16, 1991.

4 Page 7/8. Section 3.1.2: Replace the Basis in its entirety, where 1) "model of the AFRRI-TRIGA reactor" is replaced with "Model _of the AFRRI- TRIGA Reactor" and 2)

'"instumentated" is replaced with " instrumented" for grammatical correction, as follows:

Based upon the Fuchs-Nordheim mathematical model (cited by C.E. Clifford et al. in the April 1961 GA Report #2119, "Model of the AFRRI-TRIGA Reactor"), an insertion of 2.8% Ak/k results in a maximum average fuel temperature of less than 550' C, thereby staying within the limiting safety settings that protect the safety limit, The 50' C margin to the Limiting Safety System Setting and the 450' C margin to ti e safety limit amply allow for uncertainties due to extrapolation of measured data, accuracy of measured data, and location of instrumented fuel elements in the Core.

Safety Analysis: This is an administrative change to correct spelling and style. There are no safety implications.

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5. Page 8. Section 3.1.3: Replace " controls rals" with " control rods" in the first sentence of the Applicability. Replace " conditions of operations" with " condition of operation" in the last sentence of the Specifications.

Safety Analysis: These are administrath -hanges to correct spelling or style. There are no safety implications.

6. Page 22. Section 4.2.5: Replace the Specilications in its entirety as follows to clarify the requirement for fuel element surveillance and to accommodate the fuel follower control rods:

All the fuel elements present in the reactor core, to include fuel follower control rods, shall be inspected for damage or deterioration, and measured for length and bow at intervals separated by not more than 500 pulses of insertion greater than $2.00 or annually (not to exceed 15 months),

whichever occur first. Fuel elements in long-term storage need not be measured until returned to core; however fuel elements routinely moved to temporary storage shall be measured every 500 pulses of insertion greater than $2.00 or annually (not to exceed 15 months), whichever occurs first.

Safety Analysis: Fuel in long term storage is not subject to the rigors of the fuel u<ed in the reactor core. Thus damage to the fuel which may manifest itself as clongation or lateral bow is not a possibility for fuel in long-term storage.

The high degree of purity maintained in the AFRR1 TRIGA pool assures that deterioration or corrosion of the cladding will not be a problem.

7. Page 22. Section 4.2.5: Replace the 13 asis in its entirety for clarification as follows:

The frequency of inspection and measurement is based on the parameters most likely to affect the fuel cladding of a pulse reactor,'and th: utilization of fuel elements whose characteristics are well known.

The limit of transverse bend has been showa to result in no difficulty in disassembling the core. Analysis of.a worst case renario in which two adjacent fuel elements suffer sufficiently severe transverse bends to result in the touching of the fuel elements has shown that no damage to the fuel elements will resch via a hot spot or any other known 4 mechanism.

Safety Analysis: This is an administrative change in the wording to clarify the passage.

[- There are no safety implications.

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8. ' Eage 23. Section 4.3: Rcplace the liasis in its entirety as follows:

Based on experience, observation at these intervals provides acceptable surveillance of limits that assure that fuel clad corrosion and neutron activation of dissolved materials will not occur.

Safety Analysis: This is an administrative change in the wording to clarify the passage.

There we no safety implications.

9. Page 23. Section 4.4: Replace the Specifications in its entirety as follows to conform with

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latitude recommended in ANSI 15.4/7:

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D1LSpecifications:

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l The operating mechanism of the positive scaling dampers in the reactor room ventilation system shall be verified to be operable and visually inspected at least monthly.

New Spnifictdions: J The operating mechanism of the positive saling dampers in the reactor room ventilation i system shall be verified to be operable and visually inspected at least monthly (interval not

to exceed six weeks).

Safety Analysis: This is to conform with latitude recommended in ANSI 15.4/7.

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10. Pages 25. Section 5.2J: Replace the Applicability to accommodate fuel follower control rods with the following:

Applicability  :

These specifications apply to the fuel elements, to include fuel follower control rods, used

. in the reactor core.

Safety Analysis: See previously submitted safety analysis on FFCR.

11. Page 26. Section 5.Ll: Replace the part "a." of the Specifications in its entirety to accommodate fuel follower control rods with the following:

a. Uranium content: Maximum of 9.0 weight percent enriched to less than 20% uranium-235. In the fuel follower, the maximum uranium content will be 12.0 weight percent L enriched to less than 20% uranium-235.

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l. Safety Analysis: See attached safety analysis on FFCR.

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12. Page 26. Section 5.2.1: Replace the Basis in its entirety to accomm(xlate fuel follower  ;

control rods with the following: 1 A maximum uranium content of 9 weight percent in a standard TRIGA element is greater than the design value of 8.5 weight percent, and encompasses the maximum probable variation in individual elements. Such an increase in loading would result in an increase _in power density ofless than 60 An increase in local power density of 6% in individual fuel element reduces the safety margin by 10%, at most. The hydrogen-to-zirconium ratio of 1.7 will produce a maximtim pressure within the cladding well below the rupture strength

of the cladding.

The power local power density of a 12.0 weight percent fuel follower is 21 % greater than an 8.5 weight percent standard TRIGA fuel element in the D-Ring. The volume of fuel in a fuel followed nxlis 56% of the volume of a standard TRIGA fuel element. Therefore, the actual power produced in the fuel followed nx! is 33% less than the power produced in a standard TRIGA fuel element in the D-ring.

Safety Analysis: See previously submitted safety analysis on FFCR.

13. Eage 27. Section 5.2.2(e): Replace ".0625 inch" with *0.0625 inch". ,

Safety Analysis: This is an administrative change to correct style. There are no safety implications.

14. Page 27.- Section 5.2.3: Replace the part "a." of the Specifications in its entirety to accommodate fuel follower control nxis with the following:

a. The standard control rods shall have scram capability, and shall contain borated graphite, B4C powder. or boron and its compounds in solid form as a poison in aluminum or stainless-steel cladding. These nxis may have an aluminum, air, or fuel follower. If fuel followed, the fuel region will conform to the Specifications of 5.2.1."

Safety Analysis: See previously roubmitted safety analysis on FFCR. -

15. Page 27. Section 5.2.3: Replace " Scram capabilities are provided for..." with " Scram

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capabilities are provided by the ..." in the fourth sentence of the Basis.

Safety Analysis: This is an administrative change to correct style. There are no safety implications.

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16. Ege.2fLSection.5J: Replace the Grst sentence of the liasis with "The limits imposed by this specification are conservative and assure safe storage and handling.".

Safety Analysis: This is an administrative change to correct grammar. There are no safety implications.

17. Eage 29. Section_6JJ: Replace " Chairman, Radiation Sciences Department" with

" Chairman, Radiation Soarec' Depanment to administratively reflect new name. Replace

"... Control Chain, in which" with " . Control Chain in which..." in last sentence of the section.

Safety Analysis: These are administrative change- to clarify existing statements and correct grammar. There are no safety implications.

18. Eage 29, Figuirl: Replace " Chairman, Radiation Safety Department" and " Chairman, Radiation Sciences Department" with " Chairman, Safety and Fealth Dept." and " Chairman, Radiation Sources Dept." respectively. Remove " Chief, Reactor Division" in accordance with organizational change approved by the Reactor and Radiation Facility Safety Committee on July 25, 1989.

Safety Analysis: These are administrative changes to clarify existing statements. There are no safety implications.

19. Eage 30. Section 61.2: Change the Responsibility in ita entirety to clarily the responsibility of the Reactor Facility Director with the following:

The Director, AFRRI, shall have license responsibility for the reactor facility. The Reactor Facility Director (RFD) shall be responsible for administration and operation of the Reactor Facility and for determination of applicability of procedures, experiment authorizations, maintenance, and operations. The RFD may designate an individua*. who meets the requirements of Section 6.1.3.a to discharge the RFD's responsibilities in the RFD's absence. During brief absences (periods less than four hours) of the Reactor Facility Director and his designee, the Reactor Operations Supervisor shall discharge these responsibilities.

Safety Analysis: This is an administrative change to clarify existing statements, correct grammar, spelling, or panctuation. There are no safety implications.

20. Page 30. Section 6.1.3.lfa): Remove "(Reactor llranch Chief)"

Safety Analysis: This change removes obsolete terminology, there are no safety implications.

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21. Eagel0._Smicaf1M1b): Replace the requirements of Reactor operations Supervisor (ROS) in its entirety with the following:

h. Reactor Operations Supes visor (ROS)

At the time of appointment to this position, the 110S shall have 3 years nuclear experience, liigher education in a science or nuclear engineering field may fulfin up to 2 years of experience on a one-for-one basis. The ROS shall hold a USNRC Senior Reactor Operator license on the AFRRI reactor, in addition, the ItOS shall have 1 year of experience at AFRR1 or at a similar facility before .

the appointment to this position.

Justification: A year of experience at AFRRI or at a similar facility provides an adequate experience for a pers(m to assume ROS duties at AFRRI.  ;

22. - hge 3L Settlan111.2(c)(2): Heplace " Radiation Safety Depanment" with " Safety and llealth Department *,

Safety Analysis: This is an administrative change to show a change in existing terminology. There are no safety implications.

23. Eagell._Section 6.2.1.lfa): Change from " Chairman, Radiation Safety Department, AFRRl" to " Chairman, Safety and llealth Department, AFRRl" to administratively reflect 1 new name.

Safety Analysis: This is an administrative change to show a change in terminology. There are no safety implications.

24. hge 32. Section 6.212: Change from " semi annually" to " semi annually" for typographical correction.

Safety Analysis: This is an administrative change to correct grammar. There are no safety implications.

25. EagelL.Sectionh11: Replace "The activities are as follow:* hy "The activities are as follows:" to correct grammar.

Safety Analysis: This is an administrative change to correct grammar. There are no safety implications, Page 6

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26. hge 34. SectiutL6dl; Change from

• Reactor Facility Director, Reactor liranch" to

" Reactor Facility Director" and from "Reliation Safety Depanment" to

• Safety and licalth Depanment" to administratively reflect new names.

1 Safety Analysis: This is an administrative change to reflect retu ganization. The change was approval by the RRl SC meeting held on 25 July 1989. A copy of the  ;

change was sent to the USNRC on 28 July 1989

27. hge.33.3rctionhA200: Change

• Radiation Safety Department" to " Safety and llealth Department" to administratively reflect new names.

Safety Analysis: This is a. administrative chang . . n : lect reorganization. The change was .

approved by the RRFSC meeting held on 25 July 19M. A copy of the clunge was sent to the USNRC on 28 July 1989.  ;

28. hgc]L3ectionhAJ: Replace "be" ,vith "by" for grammatical correction m the second sentence.

Safety Analysis: This is an administrative change to correct grammar There are no safety implications. >

29. hge 35. Section_6.5.Ls.: Replace "be" with "by" for grammatical correction in the second sentence.

Safety Analys :: This is en administrative change to correct grammar. 'ihere are no safety 8

implications.

30. hge 3i Section 6;5.1 d.: Replace *to NRC" with "to the NRC" for grammatical correction.

Safety Analysis: This is an administrative change to correct grammar. There are no safety implications.

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1 A1TACllMENT 2 [

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