ML042790349
| ML042790349 | |
| Person / Time | |
|---|---|
| Site: | North Carolina State University |
| Issue date: | 09/28/2004 |
| From: | Cook A North Carolina State University |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML042790349 (20) | |
Text
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i 0:
US Nucle Documen
SUBJECT:
Technical License R Docket N Amendment 15 to the N(
Specifications (TS) is be TS Amendment 15 with Additional reference mal approved in 2004, an eff uilding modification aft change (TS 6.7.4) is also If the proposed changes I eing requested because completion in December December 2004, a few d; facility. The Nuclear Re completion date for the E be established.
If the proposed TS 6.7.4 submission of the annual that no period is omitted approved TS does not oc the annual operating rep(
or for the period from Ju If you have any question plqase contact Gerald WV foregoing is true and cor Anrew T. Cook Associate Director, Nucl cc:
Daniel Hi enclosures:
TS Amen Summary Additionz North Carolina State University is a land-Nuclear Reactor Program grant university and a constituent institution Nuclear Services of The University of North Carolina Department of Nuclear Engineering Campus Box 7909 Raleigh, NC 27695-7909 919.515.3347 919.513.1276 (fax)
URLwww.ne.ncsu.edu/NRP/reactor_
program.html 28 September 2004 ar Regulatory Commission t Control Desk Specification Amendment 15
-120
- o. 50-297
)rth Carolina State University PULSTAR nuclear reactor Technical ing requested. Attached, please find the affected pages for the proposed a summary and justification for each of the proposed changes.
- erial is attached for convenience. If the proposed TS changes are active date of 1 January 2005 is requested to allow for completion a fecting two of TS changes (TS 3.6 and TS 5.2). Additionally, a third TS time sensitive.
to TS 3.6 and TS 5.2 are approved, an effective date of I January 2005 is a building modification affecting these two TS is scheduled for
- 2004. If the building modification is completed as scheduled in ays will elapse with a TS requirement that is no longer applicable to the gulatory Commission will be informed if the December 2004 uilding modification can not be met so that another effective date may is approved after I January 2005, the first reporting period and date of I operating report will have to specified by the Commission to ensure from the annual operating report and that a violation of the newly cur, e.g. if the approval date is March 1" for the TS 6.7.4 change, then ort due date of April 30' may be specified for the previous calendar year ly 15' to Feb 28th.
s regarding this TS amendment request and associated information, icks at (919) 515-4601. I declare under penalty of perjury that the rect. Executed on 28 September 2004.
ear Reactor Program ighes, US Nuclear Regulatory Commission dment 15 and Justification of TS Amendment 15 Changes il Information in Support of TS Amendment 15
Summary and Justification of Technical Specification (TS) Amendment 15 Changes
- 1.
TS 3.3(i) was changed from *14 feet 2 inches to 2 14 feet 2 inches. This is a typographical error and is based on TS 2.2.1 and the fact that pool water level is a decreasing parameter. A SCRAM signal is required at or before the pool water level decreases from 20 feet to 14 feet 2 inches. This logic is the same as that used for TS 3.3(f) with the primary coolant flow rate SCRAM that occurs at 2 450 gpm with flow/flapper SCRAMs enabled. Loss of primary coolant flow rate is a decreasing parameter and therefore a SCRAM signal is required at or before the primary coolant flow rate decreases from 500 gpm to 450 gpm. All other SCRAM set points are based on increasing parameters, such as thermal power level and primary coolant temperature, so the less than or equal to symbol (*) is appropriately used and is not being changed.
- 2.
TS 3.6.a, 3.6.c, and 5.2.c eliminate references to the Primary Piping Vault (PPV) service hatch.
The PPV is an underground vault that houses primary coolant piping and the delay tank. An emergency exit is being installed at the loading dock and a walkway is being installed between the South Wing of the Burlington Engineering Laboratory and Reactor Building (refer to Figure 5.2-1 PULSTAR Reactor Site Map) on or before 31 December 2004. As a result of this modification to Burlington Engineering Laboratory, the PPV service hatch will be removed and the PPV ceiling will be sealed. A walkway will be located on top of some fill and the PPV ceiling. Also, the reactor building air intake shaft that is covered by locked, steel grates is located immediately outside the emergency exit door and will become part of the walkway. The air intake will not be affected by this building modification. Refer to the attached diagram for illustration of the PPV changes.
Changes to the two affected TS delete references to the PPV service hatch. The PPV will continue to be checked as required by TS 3.6 until the building modification is complete.
TS 5.2 is a description of reactor building design features. An effective date of 1 January 2005 is requested for this TS change to allow for completion of the building modification.
If the building modification is completed as scheduled in December 2004, a few days will elapse with a TS requirement that is no longer applicable to the facility. The removal and sealed PPV service hatch will be considered as meeting TS requirements until the new TS is effective. The NRC will be informed if the December 2004 completion date for the building modification can not be met.
Associated with this change is a similar change to the facility Physical Security Plan since the PPV is a potential entry point into the reactor building.
The Security Plan revision will be submitted as a separate document within 60 days after the change is implemented since the removal of a potential security breach is concluded to not decrease the safeguards effectiveness of the Security Plan in accordance with 10 CFR 50.5 4(p).
The changes to the TS and Security Plan are justified since a potential entry point is being removed and therefore the risk of having an unauthorized entry or security alarm failure is also completely removed. Also, having the PPV hatch removed and sealed eliminates a potential lost of reactor building negative differential pressure and/or unmonitored release path of airborne radioactivity.
- 3.
TS 3.7 was changed for consistency with ANSI/ANS-15.1-1990, The Development of Technical Specification for Research Reactors, regarding statements made on use of cryogenic liquids in experiments within the biological shield of the PULSTAR reactor and for consistency with existing TS requirements on other hazardous materials used in experiments. The current restriction on cryogenic liquids was added in TS Amendment 4 in 1978 in the new TS 3.8 for operation with fueled experiments which appeared to be in
Summary and Justification of Technical Specification (TS) Amendment 15 Changes response to US NRC Regulatory Guide 2.4 issued in 1976 which references ANSI/ANS-15.6-1974. ANSIIANS-15.6-1974 has been withdrawn and incorporated into ANSIIANS-15.1-1990. The statements made about materials used in experiments in TS 3.8 were actually applicable for all experiments. TS Amendment 11 in 1997 appropriately moved the statements made about materials used in experiments from TS 3.8 to TS 3.7 and added definitions. For a reason that is not known, the statements made in Amendment 11 on use of cryogenic liquids within the biological shield in experiments were not revised to be consistent with those contained in ANSIANS-15.1-1990 and have remained in effect to this date. Therefore, at this time the wording regarding cryogenic liquids is being changed for consistency with ANSI/ANS-15.1-1990 Section 3.8.2, which is the current applicable standard, and for consistency with other existing TS 3.7 requirements for hazardous materials used in experiments, such as materials that are corrosive, toxic, or flammable. Additional information on TS changes regarding cryogenic liquids is attached.
- 4.
TS 3.8(2) was changed from 5.5 x 108 fissions per second to 5.5 x 107 fissions per second.
This is a typographical error and is based on Section 13.2.1.6 of the FSAR. 5.5 x 107 fissions per second was used in the FSAR analyses for accidents involving fueled experiments and is equal to a thermal power level of 1.77 milliwatts (5.5 E7 f/s -3.1 E7 f/s per milliwatt). FSAR Section 13.2.1.6 is attached.
- 5.
TS 6.2.3(a) was reworded to state that the RSC/RSAC reviews and approves determinations that proposed changes to equipment, systems, tests, experiments, and procedures "meet license requirements". Specifically, the phrase "which have safety significance do not involve an unreviewed safety question" was replaced with "meet license requirements" to meet the revised 10 CFR 50.59. 10 CFR 50.59 changes became effective in March 2000. ANSIIANS-15.1-1990 Section 6.2.3(1) does not contain the phrase "which have safety significance" and therefore those words are deleted in the proposed TS 6.2.3(a). As a result, all procedures are reviewed and approved by RSAC and RSC.
- 6.
TS 6.2.3. Associate Director was deleted from receiving a summary of RSAC meeting minutes because the Director, NRP may distribute the minutes to members within the NRP.
- 7.
TS 6.2.4. Associate Director was deleted from receiving an immediate report on the deficiencies uncovered from the RSAC audit because the Director, NRP may inform or distribute the report to members within the NRP.
- 8.
TS 6.4.1. The phrase "approved Project Number can be issued by the RSC for the experiment" was replaced with "authorized experiment can be issued by the RSC" for consistency with University terminology and grammar.
- 9.
TS 6.4.2. The phrase "approved Project" was replaced with "authorized experiment" for consistency with University terminology.
- 10.
TS 6.7.4. The period of review and date of submission for the annual report was changed to a calendar year and February 28' for consistency with other reporting requiring, e.g. 10 CFR 20 requirements for personnel dosimetry and effluent. If approved, the first reporting period and date of submission will have to specified by the Commission in writing to ensure that no period is omitted and that a violation of the newly approved TS does not occur, e.g. if the approval date is March 1St for the TS change, then an annual
Summary and Justification of Technical Specification (TS) Amendment 15 Changes operating report would be due by April 30' for the previous calendar year or the period from July 1 to Feb 28h.
Conclusion The changes made in the proposed TS Amendment 15:
Are consistent with publication ANSI/ANS-15.1-1990 and the Final Safety Analyses Report as updated.
Include minor administrative changes that have no affect on the safe operation of the facility.
Include typographical corrections and terminology changes that have no affect on the safe operation of the facility.
It is concluded that the proposed changes do not reduce or compromise safety.
Additional Information for Proposed TS 3.6 and TS 5.2:
PLAN VIEW OF PPV BEFORE MODIFICATION PLAN VIEW OF PPV AFTER MODIFICATION 1p
-;I--
Z
.3 lz:z
.3 14 V-
'i 1114 1
z
,Z PLAN VIEW - PRIMARY PIPING VAULT PLAN VIEW. PRIMARY PIPING VAULT
Additional Information for Pronosed TS 3.7:
Justification for the proposed changes to Technical Specification (TS) 3.7 e. v. is provided below. A brief review of TS amendments and applicable standards is worth noting for this TS change.
I1.
The facility was licensed in 1968 and began operation in 1972. Relicensing was initiated in 1988 and was completed in 1997.
- 2.
US NRC Regulatory Guide 2.2, "Development of Technical Specifications for Experiments in Research Reactors" dated 1973 states the following in section C.2.h (regulatory position):
"The inclusion of cryogenic liquids within the biological shield of a research reactor would constitute an unreviewed safety question unless such usage has been reviewed and approved by the Commission."
- 3.
US NRC Regulatory Guide 2.4, "Review of Experiments for Research Reactors" dated 1976 references ANSI N401-1974 (ANS 15.6). No specific discussion on cryogenic liquids is given directly in Regulatory Guide 2.4. ANSI/ANS-15.6 dated 1974 has been withdrawn and incorporated into ANSIIANS-15.1, The Development of Technical Specifications for Research Reactors.
The original facility TS dated August, 1972, did not specifically discuss cryogenic liquids in TS 3.7 "Limitations on Experiments". The bases for TS 3.7 states that TS 3.7 requirements "are intended to reduce the likelihood of damage to reactor components and/or radioactivity releases resulting from experimental failure; and, serve as a guide for the review and approval of new and untried experiments by the facility personnel, as well as the Radiation Protection Council."
Additionally, the original TS 6.2.2 stated the following:
"6.2.2. The responsibilities of the RPC (Radiation Protection Council) include, but are not limited to the following:
- a.
Determination of whether a proposed change, test, or experiment would constitute an unreviewed safety question pursuant to 10 CFR 50.59
- b.
Review and approval of any untried experiment utilizing the reactor facility. The review shall include, but not be limited to a consideration of the Limitation of Experiments given in Section 3.7 of the Technical Specifications."
- 5.
The statements in TS 3.7 listed above remained in effect through TS Amendment 3.
Facility TS Amendment 4 dated 1978 added TS 3.8 "Operation with Fueled Experiments" which contained the phrase " No cryogenic liquids will be allowed within the biological shield of the PULSTAR reactor." The wording of TS 3.8 contained in Amendment 4 regarding cryogenic liquids remained in effect through Amendment 11.
- 6.
The statements in TS 6.2.2 remained in effect through Amendment 7. TS Amendment 8 dated 1984 changed TS 6.2.2.a. as follows:
"6.2.2. RPC (Radiation Protection Council) responsibilities shall include:
- a.
Review proposed tests and untried experiments which may constitute an unreviewed safety question pursuant to 10 CFR 50.59. All such reviews shall be accomplished with consideration of Sections 2 and 3 of these Technical Specifications."
- 7.
Facility TS Amendment 11 dated 1997 appropriately moved the statements made previously in TS 3.8, which applied to fueled experiments, to TS 3.7, which applied to all experiments. TS 3.7.e.v. and TS 3.7.g. applied specifically to cryogenic liquids.
Specifically TS 3.7.e.v. kept the same restrictive wording on cryogenic liquids introduced in TS Amendment 4 while TS 3.7.g defined cryogenic.
Also in Amendment 11, TS 6.2.2 was moved to TS 6.2.3 and reworded to match the wording given in ANSIIANS-15.1-1990. TS 6.2.3.c indicates that RSC and RSAC are responsible for review of experiments.
The wording of TS 3.7 and TS 6.2.3 contained in Amendment 11 remain in effect to this date with the exception of a minor title change from RPC to RSC (Radiation Safety Committee).
ANSI/ANS-15.1-1990, The Development of Technical Specifications for Research Reactors, Section 3.8.2 regarding materials used in experiments states the following:
"No material is excluded from experiments at research reactors. However, special requirements shall be established for significant amounts of special materials such as fissionable materials, explosives or metastable materials capable of significant energy release, or materials that are corrosive to reactor components or highly reactive with coolants. Requirements may range from detailed analyses to double encapsulation and prototype testing with larger amounts."
The wording of TS 3.7 was not revised in Amendment 11 to match that given in ANSIIANS-15.1-1990 Section 3.8.2, the reason for which is not known.
From the discussion above, it seems reasonable to conclude that the review of experiments and limitations on experiments as stated in the facility TS has matched the applicable standards in effect at that time until Amendment 11. ANSI/ANS-15.1-1990 Section 3.8.2 is the current standard applicable to TS for research reactors regarding materials used in experiments.
Therefore, the proposed change to TS 3.7 requested in Amendment 15 is consistent with the requirements of ANSI/ANS-15.1-1990 for materials used in experiments and with existing TS 3.7 requirements for other hazardous materials, such as materials that are flammable, toxic, or corrosive.
Additional Information for Proposed TS 3.8:
FSAR Section 13.2.1.6 Failure of a Fueled Experiment Experiments containing fissile material may be performed in the experimental facilities of the PULSTAR reactor. These experiments shall be performed in accordance with the limitations and specifications of this safety analysis to ensure that a total failure of the experiment shall be bounded by the fuel pin clad failure analysis described previously in this section. That is, the fission product inventory in a fueled experiment shall be bounded by the Fuel Pin Clad Failure analysis.
Source Term A fueled experiment at the NCSU PULSTAR facility shall be limited to contain only uranium-235 as the fissile material or fuel. The fission products directly from the fission process in the experiment constitute the source term for this analysis. A fueled experiment may be performed at a dry or wet experimental facility. The fueled experiment failure analysis presented in this section will be bounded by the fuel pin clad failure analysis.
The source term given in Table 13-16 is directly from the Fuel Pin Clad Failure analysis. It should be noted that radioiodines and radiobromines activities correspond to an underwater radionuclide release and were corrected for retention in water. The application of the fuel pin clad failure source term in this analysis results in two conservative conditions:
o Lower noble gas inventories would be produced by limiting the fission product production rate to the radioiodine and radiobromine production rates o
An underwater failed fueled experiment would result in reduced airborne radioiodine and radiobromine concentrations by retention in water of these nuclides Table 13-16 Summary of Noble Gas and Halogen Production from Fuel Pin Clad Failure Analysis Isotope Activity (Ci)t lY;i__-__t eld(%)
Br-83 1.72(10-3) 8.05(10 5) 0.51 Br-84 1.43(10 5) 3.63(104) 0.90 Kr-88 3.78(10 ')
6.78(l0-5) 3.57 I-131 8.14(104) 9.98(lO-7) 3.10 I-133 9.80(lO4) 9.26(10-6) 6.50 Xe-133 5.43(10-2) 1.53(10-6) 6.62 l
e-138 1.94(1 04) 8.15(1 04) 5.74 t
It Table 13-1 and 13-2 values ANL-5800, Reactor Physics Constants, 2nd Edition, 1963, and Reference 13-6
A calculation for the amount of fissile material and total power generated in the fueled experiment can now be performed having the source term established with Table 13-16.
Mass of Uranium-235 and Total Power Calculation The fission of one Uranium-235 atom produces two fission products. The production rate of a specific fission product is given by:
dN' = Formation Rate -
Destruction Rate dt The nuclide i will be assumed to be produced directly from thermal fission of Uranium-235 with a yield y, and the only destruction mechanism assumed will be decay; that is, transmutation is not considered in order to maximize the radionuclide concentration of interest.
Mass of Uranium-235 and Total Power Calculation The fission of one Uranium-235 atom produces two fission products. The production rate of a specific fission product is given by:
dNi = Formation Rate -
Destruction Rate dt The nuclide i will be assumed to be produced directly from thermal fission of Uranium-235 with a yield y1 and the only destruction mechanism assumed will be decay; that is, transmutation is not considered in order to maximize the radionuclide concentration of interest.
dN, d
= Yj Nf A1 N1 N1(t)
=Y-Ift 1-e-or A(t) = y 1Nf Oaf I
The analysis assumes a fueled experiment containing 400 milligrams of uranium-235 is subjected to thermal neutron fluence rates ranging from 1010 to IO' neutrons-cm-2 sec-' for continuous total exposure times ranging from 100 to 10 seconds. A sample calculation for the Br-84 activity produced in the fueled experiment is provided below. Table 13-17 summarizes the total activity generated for the isotopes in Table 13-16 for the sample calculation. Figure 13-1 provides the acceptable operating range for a 400 milligram fueled experiment.
A(10 5 ) = O.OO9xIO1 x540(lIO24) x 1.025(1021) x (1 -
e -3.63(104) X (101)
A(10 5 ) = 4.98(105) dps =
1.35(10 5) Curies
Table 13-17 Calculated Activities for a 400 milligram Fueled Experiment at a Fluence Rate of 108 n-cm s for 105 seconds Isotope j
Activity (Ci)
I Activity Limit (Ci)
Br-83 7.63(10-6) 1.72(10-3)
Br-84 1.35(10 5) 1.43(10-5)
I-131 4.40(10-6) 8.14(104)
I-133 5.87(10-5) 9.80(104)
Xe-133 1.40(10-5) 5.43(10-2)
Xe-138 8.59(l0-5) 1.94(104)
Kr-88 5.33(10-5) 3.78(10-3)
Figure 13-1 1012 1010 U
0 U)
E U
C 0
a 0~
U 0
108 107 16 10° lo 1o2 103 104 Time (Seconds) 10 5 106
TotalEnergy-Release and Power The fueled experiment energy release rate or power and total energy release for a continuous 10 5 seconds run is obtained below.
Fision rate = NF >f4 t
=
1.025(10"2) x 540(10-24) x 108
5.54(107) fissions-s i Energy release rate
200 Me V -fission -I x 5.54 (10 7 ) fissions
- s 1.11 (10'")MeV sl 1.77(10-3) watt Total energy released = 1.77(10-3 )J s-I x 105 S
=
1.77(102) Joules The analysis demonstrates that fueled experiments may be performed in experimental facilities of the PULSTAR reactor with the following conditions and limitations:
o The maximum mass of uranium-235 is limited to 400 milligrams.
o The thermal power (or fission rate) generated in the experiment is not greater than 5.5 x 108 fissions per second (1.77 milliwatt).
o The total exposure of the material is not greater than the limits set in Figure 13-1.
o The reactor shall not be operated with a fueled experiment unless the ventilation is operated in the confinement mode.
o The specifications pertaining to reactor experiments, detailed in Section 3.7 Limitations of Experiments, apply to fueled experiments.
UPDATED SAFETY ANALYSIS REPORT APPENDIX A TECHNICAL SPECIFICATIONS FOR THE NORTH CAROLINA STATE UNIVERSITY PULSTAR REACTOR FACILITY LICENSE NO. R-120 DOCKET NO. 50-297 ORIGINAL ISSUE DATE: August 25, 1972 AMENDMENT 15
NCSU PULSTAR Technical Specifications 3.3 Reactor Safety System Applicability These specifications apply to the reactor safety system channels.
Obiective The objective is to require the minimum number of reactor safety system channels which must be operable in order to assure that the Safety Limits are not exceeded.
Specifications The reactor shall not be operated unless the reactor safety system channels described in the following table are operable:
Measuring Channel
- a.
Startup Power Level(')
- b.
Safety Power Level
- c.
Linear Power Level
- d.
Log N Power Level
- e.
Flow Monitoring 2)
- f.
Primary Coolant Flow(2)
- g.
Pool Water Temperature Monitoring Switch
- h.
Pool Water Temperature Measuring Channel
- i.
Pool Water Level
- j.
Manual Button Function Inhibits Control Rod withdrawal when neutron count is s 2 cps.
SCRAM at
- 250 kW (LSSS).
SCRAM at
Enable for Flow/Flapper SCRAMs at
- 250 kW (LSSS).
SCRAM when flapper not closed and Flow/Flapper SCRAMs are enabled.
SCRAM at 2 450 gpm (LSSS) when Flow/Flapper SCRAMs are enabled.
Alarm and Manual SCRAM at
- I 170F (LSSS).
SCRAM at 2 14 feet 2 inches.
15 Amendment 15
NCSU PULSTAR Technical Specifications 3.6 Confinement and Main HVAC Systems Applicability This specification applies to the operation of the Reactor Building confinement and main HVAC systems.
Objective The objective is to assure that the confinement system is in operation to mitigate the consequences of possible release of radioactive materials resulting from reactor operation.
Specification The reactor shall not be operated, nor shall irradiated fuel be moved within the pool area, unless the following equipment is operable, and conditions met:
Equipment/Condition Function
- a.
All doors, except the Control Room and basement corridor entrance, self-latching, self-closing, and locked.
- b.
Control room and basement corridor entrance door: self-latching, self-closing and closed.
- c.
Reactor Building under a negative differential pressure of not less than 0.2" H20 with the normal ventilation system or 0.1" H20 with one confinement fan operating.
- d.
Confinement system
- e.
Evacuation system To maintain reactor building negative differential pressure (dp)."')
To maintain reactor building negative differential pressure.(2)
To maintain reactor building negative differential pressure with reference to outside ambient.(3 )
I 21 Amendment 15
NCSU PULSTAR Technical Specifications ii.
Attempts will be made to identify and limit the quantities of elements having very large thermal neutron absorption cross sections, in order to quantify reactivity effects.
iii.
Explosive material('), shall not be allowed in the reactor. Experiments reviewed by the Radiation Safety Committee in which the material is considered to be potentially explosive, either while contained, or if it leaks from the container, shall be designed to maintain seal integrity even if detonated, to prevent damage to the reactor core or to the control rods or instrumentation and to prevent any change in reactivity.
iv.
Each experiment will be evaluated with respect to radiation-induced physical and/or chemical changes in the irradiated material, such as decomposition effects in polymers.
- v.
Experiments involving cryogenic liquids(') within the biological shield or flammable materials( or highly toxic materials(X) require specific procedures for handling and shall be limited in quantity as approved by the Radiation Safety Committee.
- f.
Credible failure of any experiment shall not result in releases or exposures in excess of the annual limits established in 10 CFR 20.
('"Defined as follows (reference - "Handbook of Laboratory Safety" - Chemical Rubber Company, 4t Ed., 1995, unless otherwise noted):
Toxic:
A substance that has the ability to cause damage to living tissue when inhaled, ingested, injected, or absorbed through the skin
("Safety in Academic Chemistry Laboratories" -The American Chemical Society, 1994).
Flammable:
Having a flash point below 730F and a boiling point below I 00F. The flash point is defined as the minimum temperature at which a liquid forms a vapor above its surface in sufficient concentration that it may be ignited as determined by appropriate test procedures and apparatus as specified.
Explosive:
Any chemical compound, mixture, or device, the primary or common purpose of which is to function by explosion with substantially simultaneous release of gas and heat, the resultant pressure being capable of destructive effects. The term includes, but is not limited to, dynamite, black powder, pellet 24 Amendment 15
NCSU PULSTAR Technical Specifications 3.8 Operation with Fueled Experiments Applicability This specification applies to the operation of the reactor with any fueled experiment.
Objective To assure that the confinement leak rate and fission product inventory are within the limits used in the PULSTAR Safety Analysis and are consistent with present U. S. Nuclear Regulatory Commission guides and the Code of Federal Regulations.
Specifications Fueled experiments may be performed in experimental facilities of the PULSTAR reactor with the following conditions and limitations:
(1)
The maximum mass of uranium-235 is limited to 400 milligrams.
(2)
The thermal power (or fission rate) generated in the experiment is not greater than 5.5 x 107 fissions per second (1.77 milliwatt).
(3)
The total exposure of the material is not greater than the limits set in Figure 3.8-1.
(4)
The reactor shall not be operated with a fueled experiment unless the ventilation system is operated in the confinement mode.
(5)
The specifications pertaining to reactor experiments, detailed in Section 3.7 Limitations of Experiments, apply to fueled experiments.
Bases In the event of the failure of a fueled experiment with the subsequent release of fission products the inhalation exposure to these isotopes at any location is bounded by the Fuel Pin Clad Failure Analysis. The failed fueled experiment analysis is described in SAR Section 13.
26 Amendment 15
NCSU PULSTAR Technical Specifications 5.2 Reactor Building
- a.
The reactor shall be housed in the Reactor Building, designed for confinement. The minimum free volume in the Reactor Building shall be 2.25 x 109 cm3 (refer to SAR Section 13 analysis).
- b.
The Reactor Building ventilation and confinement systems shall be separate from the Burlington Engineering Laboratories building systems and shall be designed to exhaust air or other gases from the building through a stack with discharge at a minimum of 100 feet above ground level.
- c.
The openings into the Reactor Building are the truck entrance door, personnel entrance doors, and air supply and exhaust ducts.
- d.
The Reactor Building is located within the Burlington Engineering Laboratory complex on the north campus of North Carolina State University at Raleigh, North Carolina. Restricted Areas as defined in 10 CFR 20 include the PULSTAR Reactor Bay, Mechanical Equipment Room, Primary Piping Vault, and Waste Tank Vault.
The PULSTAR Control Room is part of the Reactor Building, however it is also a controlled access area and a Controlled Area as defined in 10 CFR 20. The facility license applies to the Reactor Building and Waste Tank Vault. Figure 5.2-1 depicts the licensed area as being within the operations boundary.
40 Amendment 15
NCSU PULSTAR Technical Specifications
- c.
A quorum shall consist of not less than a majority of the full RSC or RSAC and shall include the chairman or his designated alternate. Members from the line organization shown in Figure 6.1-1 shall not form a quorum.
- d.
RSC and RSAC shall meet at least four times per year, with intervals between meetings not to exceed six months. Both committees may also meet upon call of the Chair.
6.2.3 RSC/RSAC Review and Approval Function The following items shall be reviewed and approved by the RSC or by referral to the RSAC, as needed:
- a.
Determinations that proposed changes in equipment, systems, test, experiments, or procedures meet license requirements.
- b.
All new procedures and major revisions thereto having safety significance, proposed changes in reactor facility equipment, or systems having safety significance.
- c.
All new experiments or classes of experiments that could affect reactivity or result in the release of radioactivity.
- d.
Proposed changes to the Technical Specifications or facility license.
- e.
Violations of technical specifications or license. Violations of internal procedures or instructions having safety significance.
- f.
Operating abnormalities having safety significance.
- g.
Reportable Events (as per technical specification definition 1.22).
- h.
Audit reports.
RSC summaries and meeting minutes shall be provided to the Chancellor, Provost, Vice Chancellor for Research, Vice Chancellor for Business and Finance, Faculty Senate, and University Archives.
A summary of RSAC meeting minutes, reports, and audit recommendations approved by RSAC shall be submitted to Dean of the College of Engineering, Head of the Nuclear Engineering Department, Director of the Nuclear Reactor Program, the RSC, Director of Environmental Health and Safety, and the RSAC prior to the next scheduled RSAC meeting.
Recommendations of the annual audit made by RSAC are forwarded to the RSC for concurrence before being implemented.
50 Amendment 15
NCSU PULSTAR Technical Specifications 6.4 Review of Experiments 6.4.1 New (untried) Experiments All new experiments or class of experiments, referred to as "untried" experiments, shall be reviewed and approved by the Associate Director of the Nuclear Reactor Program, Reactor Health Physicist, and the Radiation Safety Committee (or RSAC as applicable), prior to initiation of the experiment.
The review of new experiments shall be based on the limitations prescribed by Technical Specifications 3.7 and 3.8 and other Nuclear Regulatory Commission regulations, as applicable. If the Radiation Safety Committee, the Associate Director of the Nuclear Reactor Program, and the Reactor Health Physicist jointly agree that the experiment can be safely performed within the limitations of the technical specifications and other applicable Nuclear Regulatory Commission regulations, then an authorized experiment can be issued by the RSC.
6.4.2 Tried Experiments All proposed experiments are reviewed by the Reactor Operations Manager and the Reactor Health Physicist (or their designated alternates). Either of these individuals may deem that the proposed experiment is not adequately covered by the documentation/analysis associated with an existing authorized experiment and therefore constitutes an untried experiment that will require the approval process detailed under Technical Specification 6.4.1. If the Reactor Operations Manager and the Reactor Health Physicist concur that the experiment is a tried experiment, then the request is approved and the experiment can be scheduled within the limitations of the reactor operating schedule.
Substantive changes to previously approved experiments shall be made only after review and approval by the Associate Director of the Nuclear Reactor Program, Reactor Health Physicist, and the Radiation Safety Committee (or RSAC as applicable).
53 Amendment 15
NCSU PULSTAR Technical Specifications 6.7 Reporting Requirements 6.7.1 Reportable Event For Reportable Events as defined by section 1.22 of these specifications, there shall be a report not later than the following work day by telephone to the Nuclear Regulatory Commission Operations Center followed by a written report within 14 days that describes the circumstances of the event.
6.7.2 Permanent Changes in Facility Organization Permanent changes in the facility organization involving either Level I or 2 personnel (refer to specification 6.1) shall require a written report within 30 days to the Nuclear Regulatory Commission Document Control Desk.
6.7.3 Changes Associated with the Safety Analysis Report Significant changes in the transient or accident analysis as described in the Safety Analysis Report shall require a written report within 30 days to the Nuclear Regulatory Commission Document Control Desk.
6.7.4 Annual Operating Report An annual operating report is required to be submitted no later than February 28th of each year and will cover the period of January 1st through December 3 1st. The report is transmitted to the Document Control Desk, Nuclear Regulatory Commission, Washington.
The annual report shall contain as a minimum, the following information:
- a.
A brief narrative summary:
- i.
Operating experience including a summary of experiments performed.
ii.
Changes in performance characteristics related to reactor safety that occurred during the reporting period iii.
Results of surveillance, tests and inspections.
- b.
Tabulation of the energy output (in megawatt days) of the reactor, hours reactor was critical, and the cumulative total energy output since initial criticality.
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