ML20036B396

Safety Evaluation Supporting Amend 177 to License DPR-37

ML20036B396
Person / Time
Site:	Surry
Issue date:	05/14/1993
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20036B395	List: ML20036B394 ML20036B396
References
NUDOCS 9305190418
Download: ML20036B396 (11)

Text

{{#Wiki_filter:-. [ (MTED STATES NUCLEAR REGULATORY COMMISSION l e 3.c,c g 5 C W ASWNGTON. D. C. 20555 \\...+/ l SAFETY' EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ) RELATED TO AMENDMENT NO. 177 TO I i FACILITY OPERATING LICENSE NO. DPR-37 I VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION. UNIT N0. 2 l DOCKET NO. 50-281 i 4

1.0 INTRODUCTION

j By letter datd May 6,1993, the Virginia Electric and Power Company (the licensee) requested an emergency Technical Specification (TS) change for Surry Power Station, Unit 2. The proposed change would allow operation with a 100 psi reduction in the reactor coolant system (RCS) nominal operating pressure l l through the end of Cycle 12. l

2.0 BACKGROUND

i i j On April 29, 1993, during hydrostatic testing of the Surry, Unit 2 prior to returning to operation following completion of the Cycle 11 refueling outage, RCS leakage past the pressurizer "A" and "C" safety valves was observed. The licensee attributes the leakage to the loss of the water loop seal upstream of the safety yalves. The hydrostatic testing was terainated and the RCS l pressure reduced to prevent further leakage through the safety valves. To i complete the ASME-required hydrostatic test and to prevent further leakage past the safety valves, the licensee found it necessary to mechanically secure (gag) the safety valves. Mechanically securing the leaking pressurizer safety valves was evaluated as an acceptable method to aid in the reseating of the valves and completing the required hydrostatic test without potentially increasing the leakage from the safety valves. The Surry TS requires that all three safety valves be operable with the RCS temperature greater than 350*F. ~ Since the "A" and "C" safety valves would be gagged, and therefore inoperable, i the licensee requested and was granted on April 30, 1993, a 36-hour l enforcement discretion to perform the hydrostatic test with the "A" and "C" valves gagged with the RCS temperature greater than 350*F. The hydrostatic 3 test was successfully completed; however, loop seals to all the valves could l not be established due to continued leakage. t Following completion of the testing described above and with the gags removed and the RCS pressure reduced to normal operating pressure (2235 psig), the "A" safety valve continued to show minor leakage. The RCS pressure was reduced to 1800 psig and slowly repressurized to 2135 psig where the "A" safety valve stabilized. The licensee indicated that despite refurbishing and resetting r the lift point, they had experienced difficulty with the same safety valve l i 9305190418 930514 ~- DR ADDCK 05000281 PDR

= l i i i i during past start-ups and, therefore, further refurbishing of the "A" valve j was not likely to eliminate the leakage. By letter dated May 4, 1993, the j licensee requested and was granted an enforcement discretion to operate Surry, Unit 2 at reduced nominal operating pressure (2135 psig) to eliminate leakage until the NRC had received and processed an emergency TS change. By letter dated May 6, 1993, the licensee requested an emergency TS amendment to allow j i operation of Surry, Unit 2 at an RCS nominal operating pressure of 2135 psig, J instead of the normal 2235 psig for the duration of Cycle 12. l 3.0 PROPOSED TS CHANGES I e 1 Limits on RCS average temperature, pressurizer pressure, and RCS flow are l j specified to assure that each of the parameters is maintained within the normal, steady-state envelope of operation assumed in the transient and a l accident analyses. The licensee has stated that these limits have been analytically demonstrated to be adequate to maintain a minimum departure from f l nucleate boiling ratio (DNBR) which is greater than the design limit j throughout each analyzed transient. The proposed changes include a decrease- { in the specified minimum pressurizer pressure from 2205 to 2105 psig. The i effect of this decrease on DNBR margin has been evaluated by the licensee and has been determined to maintain an adequate margin. 2 i 1 i Basis Sections of Technical Specifications 2.1. 2.2. and 3.3 The Basis sections of these TS are revised to reflect the change in RCS nominal operating pressure from 2235 to 2135 psig and the reduction of the i high pressurizer pressure reactor trip setting limit from 2385 to 2310 psig. j In addition, the Basis section of TS 2.3 is revised to reflect a reduction in i the power-operated relief valve (PORV) nominal setting from 2335 to 2235 psig. l l The setpoint change assures that the PORVs will provide a diverse source of I i RCS overpressure protection prior to reaching the high pressurizer reactor trip setpoint. i Specific chances i l l Technical Specification 2.3A.2(b) - Instrument Settina limit for Hioh Pressurizer Pressure Reactor Trip i This specification provides the setting limit for the high pressurizer l pressure reactor trip as follows: 1 1 (b) High pressurizer pressure - s 2385 psig 1 j The proposed changes would modify this item as follows: (b) High pressurizer pressure - s 2385* psig l p j s 2310 psig for Unit 2 Cycle 12 operation at Reactor Coolant l j System nominal operating pressure of 2135 psig. i i . t l ~ l t 1 [

- Technical Specification 3.12.F.1 - DNB Parameters This specification provides for a minimum pressurizer pressure to be maintained during power operation as follows: Pressurizer Pressure 2 2205 psig The proposed changes would modify this item as follows: Pressurizer Pressure 2205* psig 2 2105 psig for Unit 2 Cycle 12 operation at Reactor Coolant System nominal operating pressure of 2135 psig. Basis Sectjon for Technical Specification 2.1 - Safety limit Reactor Core This Basis section states the following: ... based on steady state nominal operating power levels less than or equal to 100% steady state nominal operating Reactor Coolant System average temperatures less than or equal to 574.4*F and a steady state nominal operating pressure of 2235 psig." The proposed. changes would modify this discussion as follows: ... based on steady state nominal operating power levels less than or equal to 100% steady state nominal operating Reactor Coolant System average temperatures less than ar equal to 574.4*F and a steady state nominal operating pressure of 2235 psig." For Unit 2 Cycle 12, Reactor Coolant System nominal operating pressure may be reduced to 2135 psig. Basis Section for Technical Specification 2.2 - Safety Limit Reactor Coolant System Pressure This Basis section states the following: "The nominal settings of the power-operated relief valves at 2335 psig, the reactor high pressure trip at 2385 psig, and the safety valves at 2485 psig are established to assure never reaching the Reactor Coolant System pressure safety limit." The proposed changes would modify this discussion as follows: "The nominal settings of the power-operated relief valves at 2335* psig, the reactor high pressure trip at 2385** psig, and the safety valves at 2485 psig are established to assure never reaching the Reactor Coolant System pressure safety limit." 2235 psig for Unit 2 Cycle 12 operation at Reactor Coolant System nominal operating pressure of 2135 psig.

. ~, .~ . L $; 2310 psig for Unit 2 Cycle 12 operation at Reactor Coolant System nominal operating pressure of 2135 psig. l l Basis Section for Technical Specification 3.3 - Safety In.iection System i 4 This Basis section states the following: I ] "The operating pressure of the Reactor Coolant System is 2235 psig... j The proposed changes would modify this discussion as follows: "The operating pressure of the Reactor Coolant System is 2235* psig..." For Unit 2 Cycle 12, Reactor Coolant System nominal operating pressure f may be reduced to 2135 psig. l a i j 4.0 DISCUSSION i The major issues considered in the evaluation of the proposed changes were (1) ) departure from DNBR performance margins, (2) the impact on transient performance parameters other than DNBR, and (3) fuel performance margin. 5 DNBR Performance Marains l f i The licensee assessed the impact of the RCS operating pressure reduction on l l the analyses for DNBR-limited events. For events protected by the l overtemperature AT (OTAT) reactor trip, the licensee determined that there is no impact due to_the reduced operating pressure. For DNBR-limited events not l protected by the OTAT reactor trip, the licensee determined that the DNBR i l penalty resulting from the reduced operating pressure would be accommodated by i the retained margin in its approved DNBR methodology. The licensee concluded i that the results for all DNB-limited events will continue to be bounded by the i currently applicable licensing basis analysis for reduced pressure operation. i Non-DNB Accident performance l l In addition to the assessment described above for impact upon events limited by DNBR considerations, the licensee assessed potential indirect impacts from l i operation at reduced RCS pressure. The assessment of impact from reduced RCS l pressure operation resulted in events being placed into one of three j ] classification categories: (1) No Impact, (2) Potentially Impacted, and (3) 4 Impact Requires Quantification. Events in each category are summarized below. 1 1 (1) No Impact l 1 5 From its assessment, the licensee determined that the following events are insensitive to initial RCS pressure conditions, because the acceptance criterion is either not related to RCS pressure or initial pressure does not i ] directly influence transient behavior. i l Uncontrolled Control Rod Assembly Withdrawal from Subcritical ] Condition i i t ? 4 m< ~,.

. Chemical and Volume Control System Malfunction (Boron Dilution) Startup of an Inactive Reactor Coolant Loop Excessive Heat Removal Due to Feedwater System Malfunction Excessive Load Increase Incident Fuel Handling Accidents Volume Control Tank Rupture Waste Gas Decay Tank Rupture Loss of Coolant Accident (Small and large Break) Rupture of a Main Steam Line (2) Potentially Impacted The licensee identified events in this category that s ther have RCS pressure as the key safety analysis acceptance criterion or have the potential for initial RCS pressure to influence transient behavior during the event. The licensee evaluated these events and concluded that limiting conditions were either insignificantly impacted (or were beneficially impacted) by reduced initial RCS pressure. Loss of Normal Feedwater Loss of All Alternating Current Power to the Station Auxiliaries Steam Generator Tube Rupture Rupture of a Control Rod Drive Mechanism Housing (Control Rod Assembly Ejection) Main feedline Break Locked Reactor Coolant Pump Rotor (Overpressure Evaluation) (3) Impact Requires Quantification The licensee identified one event in this category - the Loss of External Electrical Load. This event establishes the limiting conditions for RCS overpressurization, which is influenced by initial RCS pressure. The licensee stated that previous sensitivities have demonstrated that operation at reduced RCS pressure causes the predicted peak RCS pressure for this event to increase, assuming all other assumptions and protection system actions remain unchanged. The key reactor protection system function which terminates the event is the reactor trip on high pre;,surizer pressure. Peak RCS pressure is predicted to be greater than in the design analysis for operation at reduced initial pressure, since the primary-secondary energy imbalance exists for a

1 I-i j 1 longer time interval. This causes more energy deposition la the RCS and greater pressurization. The specific overpressurization event of interest was a complete loss of load transient from an initial pressure of 2105 psig (2235 psi - 100 psi reduction - 30 psi errors) combined with a 75 psi reduction in the assumed high i pressurizer pressure reactor trip setpoint. The pressurizer safety valve relief behavior was modeled using the approach described in WCAP-12010, which was recently approved by the NRC. Consistent with the NRC's SER on thi.s methodology, a 1% valve setpoint shift was assumed, since the Surry valves are l tested in a steam environment and operate with water loop seals in their l installed configuration. An isothermal temperature coefficient of reactivity i which bounds the beginning of core life TS limit (+3 pcm/T) was assumed. The i licensee's assessment determined that a peak RCS pressure of 2726 psig would l 1 result for this case. I i Fuel Performance Assessment 3 } The licensee reviewed the fuel rod design criteria to assess the impact of a I l reduction in RCS pressure frcm 2235 psig to 2135 psig for Surry Unit 2 Cycle i 12 operation. A reduction in RCS pressure can impact the rod internal i j pressure evaluaticn since the differential between the fuel rod internal pressure and the RCS pressure result in an increase in the fuel-to-clad gap. The licensee reanalyzed the rod internal pressure evaluation at the reduced system pressure of 2135 psig and it was determined that all design criteria j will continue to be met. i j 5.0 EVALUATION i A l Technical Soecification 2.3. A.2.(b) - Instrument Settina Limit for Hioh Pressurizer Pressure Reactor Trio j The function of the high pressurizer pressure reactor trip is to protect the i RCS and its various components from overpressurization. Reduction of the high l pressurizer pressure reactor trip setting limit from 2385 psig to 2310 psig is required to assure that an RCS overpressurization event does not cause RCS pressure to exceed the ASME Section III transient pressure limit of 110% design pressure. Reduction of the setpoint is necessary due to greater l pressure overshoot during an overpressure transient. With initial RCS pressure 100 psi below the normal value, peak pressure could exceed the transient limit (2735 psig) unless the high pressurizer pressure trip setpoint is reduced. The licensee determined that the proposed reduction of the j setting limit is adequate to provide the required overpressure protection. { j This result is below the applicable pressure criterion (i.e., s;110% of design j pressure, or 2735 psig), and is therefore acceptable. l Technical Specification 3.12.F.1 - DNB Parameters i I ~ 2 l Limits on RCS average temperature, pressurizer pressure, and RCS flow are j specified to assure that each of the parameters is maintained within the normal, steady state envelope of operation assumed in the transient and accident analysis. These limits have been analytically demonstrated by the i i l 2 I d

i J )

l 4

j licensee to be adequate to maintain a minimum DNBR which is greater than the design limit throughout each analyzed transient. The proposed changes j decrease the specified minimum pressurizer pressure from 2205 to 2105 psig. 1 1 The effect of this proposed decrease on DNBR margin has been evaluated and [ j-adequate margin is maintained. ) Basis Sections of Technical Specifications 2.1. 2.2 and 3.3 i The Bases of these Technical Specifications are revised to reflect the change l 5 in RCS nominal operating pressure from 2235 to 2135 psig and the reduction of l 4 the high pressurizer pressure reactor trip _ setting limit from 2385 to 2310 l psig. In addition, the Basis Section of Techrical Specification 2.3 is { l revised to reflect a reduction in PORY nominal setting from 2335 to 2235 psig. i The setpoint change assures that the PORVs will provide a diverse source of i RCS overpressure protection prior to reaching the high pressurizer pressure reactor trip setpoint. In summary, based on the licensee's reanalysis, the NRC staff concludes that, using the proposed TS values, operation of Surry, Unit 2 will maintain the e l existing accident analysis margins and there is reasonable assurance that the i RCS pressure will be maintained at less than 110 percent of the design l l accident conditions. l 6.0. EMERGENCY CIRCUMSTANCES ( 10 CFR 50.91(a)(5) requires that whenever an emergency situation exists, a j licensee must explain why this emergency situation occurred and why it could not avoid this situation, and the NRC will assess the licensee's reasons for failing to file an application sufficiently in l advance of that event. An emergency situation exists when the NRC's failure i to act in a timely way would result in derating or shutdown of a nuclear j plant, or in prevention of either resumption of operation or of increase in i power output up to the plant's licensed power level. In such cases, the NRC may issue a license amendment involving no significant hazards consideration without prior notice and opportunity for a hearing or for public comment. Our discussion of why this proposed change meets the conditions necessary for j emergency consideration is provided below. ( ( l Why Emeroency Situation Occurred and Could Not be Avoided l / On April 29, 1993, hydrostatic testing of the Unit 2 Reactor Coolant System I l (RCS) was being performed in accordance with Section XI of the ASME Code after modifications to the resistance temperature detector bypass lines and l replacement of a safety injection check valve. During the hydrostatic test j with an RCS pressurc of 2278 psig, indication of discharge from the "A" and "C" pressurizer safety valves was observed. The RCS minor leakage from the j "A" and "C" pressurizer safety valves occurred at the hydrostatic test l pressure and continued at normal operating pressure. i Technical Specification 3.1.A.3.a requires that all three pressurizer safety i valves be operable when the head is installed on the reactor and RCS l l temperature is above 350*F. Mechanically securing the leaking pressurizer i l l ~

i ) t i safety valves was evaluated as an acceptable method to aid in the reseating of i the valves and completing the required hydrostatic test without potentially increasing leakage from the safety valves. In order to mechanically secure the safety valves, enforcement discretion from the requirement of TS 3.1. A.3.a was necessary. The enforcement discretion was requested and received on 4 April 30, 1993. This enforcement allowed two safety valves to be mechanically secured for 36 hours. On May 1, 1993, the "A" and "C" safety valves were mechanically secured and the hydrostatic test was completed. However, when the mechanical securing i devices were removed following the test and RCS pressure was returned to i j normal operating pressure (2235 psig), indications from the pressurizer relief j tank, safety valve acoustic monitors, and tail pipe temperature detectors continued to indicate minor leakage of the "A" safety valve. Reducing RCS t j pressure to approximately 1800 psig and holding at that pressure resulted in i ] the leakage stopping and the associated safety valve temperature profile i stabilizing, indicating reformation of the loop seal for the "A" safety valve. j a 4 r On May 3,1992, RCS pressure was slowly increased to and held at 2135 psig l without any further indication of the leakage phenomenon experienced i previously. It was determined then, based on the most recent leakage r experience, to request a lowering of RCS operating pressure for Cycle 12 i operation as a conservatively prudent action. Operation with a reduced RCS 1 pressure will provide additional margin between valve leakage at power, which j can result in valve seat damage, and any consequential plant transient that may result from increased RCS leakage. l Operation of Unit 2 at a reduced RCS pressure of 2135 psig was evaluated and l found acceptable. In order to allow reduced pressure operation, changes to 2 the TS are required. Technical Specification 3.12.F.1 requires that RCS j pressure be maintained ;t2205 psig during power operation and Technical Specification 2.3.A.2(b) requires that the high pressurizer pressure reactor 4 l trip setting be 3;2385 psig. To ensure continued overpressure protcction and DNBR margins at the proposed reduced operating pressure, these limits require i revision. Discretionary enforcement from the requirements of Technical i Specifications 3.12.F.1 and 2.3.A.2.(b) was requested and granted on May 4, i 1993 to allow resumption of Unit 2 operation. The licensee submitted a proposed emergency TS change within the provisions of that discretionary enforcement action to allow continued operation of Units 2 at reduced RCS j pressure through the end of Cycle 12. l l Basis for Emeroency TS Chance Reauest i l Continued operation of Unit 2 at reduced RCS pressure is proposed as a conservatively prudent action to increase the margin between operating i i pressure and the onset of valve leakage which has been experienced during the i recent hydrostatic testing. Furthermore, the pressurizer safety valves are operable in their present condition and the unit can be safely operated at the proposed reduced RCS pressure. Operation at reduced pressure creates no safety consequences, as discussed in Sections 4.0 and 5.0 above. The safety l valves were removed, tested, and refurbished during the recently completed j j refueling outage. The as-left lift setpoints were within TS limits. i i l 1 4 [

l t, The observed minor safety valve leakage was believed to be the result of differential thermal expansion and the resultant slight misalignment of valve l internals. Minor valve discharges can occur until internal stresses are .i relieved. This minor leakage is not indicative of a setpoint shift or other cperability concern. The minor leakage which occurred on Unit 2 has no effect 1 on the safety valve lift pressure or relieving capability. The licensee has j 4 concluded that the Unit 2 pressurizer safety valves are operable and that there is no safety or operational reason for placing the unit in cold shutdown ] for additional valve maintenance. Furthermore, based on the licensee's i understanding of the phenomenon, valve maintenance is not likely to preclude a reoccurrence of valve leakage upon subsequent restart. The licensee does not i have a spare pressurizer safety valve and the long lead-time to purchase a new 3 valve (approximately 12 to 14 months) would result in a forced shutdown for that time period. j While minor safety valve leakage in itself is not harmful, such leakage can i lead to loss of the loop seal and steam cutting of valve seats if allowed to persist. Modifications which will reduce the potential for leakage are j scheduled to be implemented during each unit's next refueling outage. The j modifications will drain the loop seals, replace the safety valves with valves j suitable for steam service, and eliminate the loop seal ovens. The loop seal 1 ovens increase the propensity for leakage by maintaining high safety valve temperatures. Failure to receive approval of the proposed Technical Specification changes on an emergency basis will increase the risk of RCS leakage and may necessitate a plant shutdown. Based on the recent experience, operation of Unit 2 at the normal RCS pressure of 2235 psig could result in the resumption of minor j safety valve leakage. Continuing leakage would lead to steam cutting of the safety valve seats and increasing RCS leakage. With this concern in mind, the licensee has concluded o i that operation at a reduced RCS pressure, which provides increased margin between operating pressure and the onset of valve leakage, is both prudent and ] conservatively safe. Since reduced RCS pressure operation is considered l necessary to resume full power operation of Unit 2, this request satisfies the criteria of 10 CFR 50.91(a)(5) for an emergency situation. Without approval of the emergency TS change, a forced shutdown of Surry, Unit 2 for an j indefinite period would be required. j

7.0 FINAL NO SIGNIFICANT HAZARDS CONSIDERATION

DETERMINATION i 1 The Commission's regulations in 10 CFR 50.92 state that the Commission may l make a final determination that a license amendment involves no significant j hazards consideration if operation of the facility in accordance with the amendment would not: (1) Involve a significant increase in the probability or consequences j of an accident previously evaluated; or l 1 (2) Create the possibility of a new or different kind of accident from i i any accident previously evaluated; or d

. (3) Involve a significant reduction in a margin of safety. The licensee stated that the proposed TS change did not involve a significant hazards consideration, stating that the proposed TS changes will not: 1. Involve a significant increase in the probability or consequences of an accident previously evaluated. The probability of any accident previously analyzed is not increased. Pressurizer safety valves continue to be operable and capable of performing their intended function. Operating at a reduced RCS pressure does not affect the frequency of accident initiating events. Although the Reactor Coolant System pressure is reduced for one cycle of operation, the departure from nucleate boiling ratio (DNBR) margin is maintained for accidents that challenge the DNBR limits. The loss of load analysis with the modified high pressurizer pressure reactor trip setpoint continues to meet the overpressure design limit. Therefore, there is no increase in the consequences of any accident previously evaluated which is created by operation of Surry Unit 2 at reduced pressure. Furthermore, the proposed changes are being made to provide increased margin between operational pressure and the onset of safety valve leakage. This reduces the potential for valve seat damage and any consequential plant transients that may result from increased RCS leakage. 2. Create the possibility of a new or different kind of accident from any previously evaluated. There are no new failure modes or mechanisms associated with operating Surry Unit 2 at reduced pressure for up to one cycle. Furthermore, the proposed changes are being made to provide increased margin between operational pressure and the onset of safety valve leakage. This reduces the potential for valve seat damage and any consequential plant transient that may result from increased RCS leakage. Therefore, there are no new or different kind of accidents created by operation of Surry Unit 2 at reduced pressure. 3. Involve a significant reduction in the margin of safety. The limiting DNB analyses continue to meet the DNBR acceptance criteria at reduced pressure operation. The applicable overpressure safety analyses acceptance criteria continue to be met with the high pressurizer pressure reactor trip setpoint reduced to less than or equal to 2310 psig. Therefore, the i existing margin of safety is safety is not reduced by operation of Surry Unit 2 at reduced pressure. I Based on its evaluation of the above, the staff concurs with the licensee's analysis and, therefore, concludes that this amendment meets the criteria, and does not involve a significant hazards consideration.

8.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Virginia State official i

I was notified of the proposed issuance of the amendment. The State official had no comment.

9.0 ENVIRONMENTAL CONSIDERATION

This amendment changes a requirement with respect to installation or use of a L facility component located within the restricted area, as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluent that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has made a final no significant hazards finding with respect to this amendment. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.

10.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) the amendment does not (a) significantly increase the probability or consequences of an accident previously evaluated, (b) increase the possibility of a new or different kind of accident from any previously evaluated or (c) significantly reduce a safety margin and, therefore, the amendment does not involve a significant hazards consideration; (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; (3) such activities will be conducted in compliance with the Commission's regulations, and (4) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. Principal Contributors: Bart Buckley Frank Orr Date: May 14, 1993 I i i

p-- l NRC FORiA 374 1 4 ',l O U.S. NUCLE An OtEG,ULATO,RY COMMISSION g '*"E O' "^GESh g. p p.cs) V l MATERIALS LICENSE Amendment No. 62 l1 l 1 g Pursuant to the Atomic Energy Act of 1954. as amended, the Energy Reorganization Act of 1974 (Public Law 93 438), and Title 10 ll Code of Federal Regulations, Chapter I, Parts 30,31, 32. 33,34, 35. 39,40 and 70, and in rehance on statements and representations hereto jp R' made by the licensee, a license is hereby issued authorizing the licensee to receise, acquire, possess, and transfer byproduct, source, and special ,5 I nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to deliver or transfer such material I to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This IP eM dall be deemed to contain the conditions ! l specified in section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicrA des, regulations and orders of the Nuclear ( g Regulatory Commission now or hereafter in effect and to any conditions specified below. l g In accordance with letter dated i April 8, 1992, I

1. Department of the Army

3. Ucense number 08-01738-02 is amended in f

l Walter Reed Army Medical Center (WRAMC) its entirely to read as follows. g n 's g

2. Washington, D.C.

20307-5001 'gl t -[

4. Expiration date April 30, 1993 lll l

5. Docket or y 030-01317 l l g

gli Reference No i (

6. Byproduct, source, and/or fu

7. Chemical and/or physical e 6. Maximum amount that hcensee 1

E I{ special nuclear material form U. may possess at any one time f ' ? cnder this license

5i g

n ,n a ,y -g y - ~ ,a i A. Any byproduct material with 'AfAny, / fd : if A. 400 millicuries of each il l radionuclidewithatotalj! atomic numbers 1 ^ p;[ / ~ \\ s { }? ; piifsession limit of 26 g ( g O(xn4fx' curies s B. Iodine 131 t B.1Any ,'. B. 2ccuries l: E C. Xenon-133 in biC?Anyv'!p'J'V N . ' ; C. 22c~uries I D. Krypton 85 M "D._,Afly d L - D. IRcurie Z E.- Anyd l I i!I c> - ' E..M' curies E E. Gold 198 n i urie i lG. Carbon 14 G F4 _Any M l 1I W 3 W F.02 F. Phosphorus 32 %\\V q GFAny.' ' ~ "~~ $ - G 2 curies g{H. Iodine 125 O;; J1DI curie i '/ H. Any G N. f,h'f)J.Any - ~ ,. [" J. 750 millicuries j Ij I. Iridium 192 I. Any / 'O ph I curie E J. Chromium 51 E K. Sulfur 35 K. Any \\ K. I curie lg lit. Hydrogen 3 L.?Any, L. 5 curies l[ ! M. Molybdenum 99 M."Mol.ibdenu'm 99/T M. 23 curies t t Techneti6ni 99m

g E

Generators lNi R N. Technetium 99m N. Any N. 23 curies I

0. Strontium 90

0. Sealed sources

0. 500 millicuries S

l P. Cesium 137 P. Sealed sources P. 2 curies f; g (3M 6D6C-CA) Q. Gadolinium 153 Q. Sealed sources Q. 2 curies I' R. Iodine 125 R. Sealed sources R. 400 millicuries l l oe 8 A) S. Iodine 125 S. Sealed sources S. 500 millicuries l g T.4 sources,nottoexce g (3M Company seeds) T. Iodine 125 T. Sealed sources I (AECL Models C235 or 300 millicuries each l 9305190136 930415 i PDR ADOCK 03001317 0324, or Amersham Core

• i l

C PDR Model IMC.P2) 5 OFFICIAL RECORD COPY ML 10 'ji .e,-- r - w - - - -- - - - m _ _ _ _ _ _ w_ _ - m - - - - -- --- - _ _ _ - r _ _ _ m - - _ _ _s t

I aG 8 "3 e r os l Licen,e number !l l g 08-01738-02 I ( MATERIALS LICENSE y/ 3,,,,,,,g,,,,,,,,,,,,,, l SUPPLEMENTARY SHEET i 030-01317 l Amendment No. 62 { I q (Itcms 6., 7. & 8. continued) { j j i i (

6. Byproduct, source, and/or

7. Chemical and/or physical

8. Maximum amount that i

l 8 special nuclear material form l licensee may possess at i any one time under this I ] q license i ( U. Cesium 137 U. Sealed sources U. 1,200 millicuries l 4 V. Cobalt 60 V. Sealed sources V. 500 millicuries I W. Americium 241 W. Any W. 100 microcuries i t X. Americium 241 X. Sealed sources. X. 20.5 curies i i l u(Monsinto Model. NRC, q '. '2704) l 4 Y. Nickel 63 . Y. Sealed sources and foils Y. I curie j 'l Z. lodine 129 Z. Sealed sources ~Z. I curie i 8 AA. Thorium AA. Any AA. 5 kilograms i l BB. Uranium BB. Any BB. 50 kilograms t 4 CC. Uranium depleted in CC. Plated Metal CC. 400 kilograms q Uranium 235 4 DD. Americium 241 DD.~ Sealed sources DD. 200 millicuries I ( EE. Cesium 137 ( EE.'~ Sealed source \\ / EE. 150 curies ' (American Nuclear? l l

. Corporation Ho' del? 127)

~ i 'i ~t g FF. Cesium 137 , FF.JSealed source's-FF. 50 millicuries g '(3M 6D6C4CA); J2 ^ s i i ! } } t L~ ~; ~ }9. Authorized use ,, : p; 7 j ,s 3 A. through T. Medical research, diagnosis, and therapy; research and development 1 1 as defined in 10 CFR 30.4. ! l U. through Z. Research and development as defined in 10 CFR-30.4; teaching. lj AA. and BB. Teaching and laboratory research. ^

J CC.

Shielding. i' l DD. Standards and reference sources.' f3 i, EE. In an Eberline Instrument Corporation Model 8150-150 CS for calibration of !1 i instruments. FF. Instrument calibration. {l l \\ CONDITIONS ij g 10. Location of use: Walter Reed Army Medical Center, Washington, D. C.; t WRAMC Forest Glen Section and Annex, Silver Spring, Maryland; Walter Reed Army l E Institute of Research Animal Holding Facility, Fort Meade, Maryland; U.S. Army 4 Medical Laboratory, WRAMC Department of Pathology, Fort Meade, Maryland; i l and U.S. Army Institute of Dental Research Facility, Fort Meade, Maryland; Rickman Building, 13 Taft Court, Rockville, Maryland; Key West Research Center, g g. 9620 Medical Center Drive, Rockville, Maryland. l l 1 i J 11. Radiation Safety Officer: LTC Arthur G. Samiljan. i k I ( .P) R ul VV eimfr;rmaammes,rzar.zsEErmrmras%KfrarmrazzasrmarmaaxramrairX i

p.m.. -*** h...m ..mmmm s&TETrM*- .w..=*w-mmmmm..., l N3C f orm 374A U.S.N AR MCULATORY COMMISslON 3 4 e w ,,gg og pgggg l M *3 License number I l/ g 08-01738-02 l q MATERIALS LICENSE coctei oi Rercience number ( SUPPLEME NTARY SHE ET W 030-01317 / li l Amendment No. 62 4,I ( (Continued) CONDITIONS E ( 12. A. Licensed material shall be used by, or under the supervision of, individuals h( l designated by the licensee's Radiation Safety Committee, Col. Joan T. Zajtchuk, Chairman. g y j i B. The use of licensed material in or on humans shall be by a physician as defined l l i s in Section 35.2 of 10 CFR Part 35. I l i U C. Physicians designated to use licensed material in or on humans shall meet the l training criteria established jp 10 CFR Part 35, Subpart J. i I q 4 q 13. Experimental animals administered licensed materials.or their products shall not be 4 used for human consumption. ( h In lieu of using the conventional radiation caution colors (magenta or purple on

f-8 14 yellow background) as 'provideo in Section 20.203(a)(1), of 10 CFR Part 20, the p

3 licensee is hereby authorized,to label detector cells and cell baths, containing i ( licensed material and used in gas chromatography devices, with conspicuously etched y ( or stamped radiation caution-symbols without a color requirement. 1 E i /S P i 7-I 15. Detector cells containing a titanium tritide foilfor a scandium tritide foil shall l only be used in conjunction with'a properly' operating temperature control mechanism (f 2 g which prevents foi1 temperatures

• from exceeding that specified by the manufacturer.

i i . l } > !!!) ? ij V i

16. Notwithstanding the= requirements of -10 CFR $5.49 (a) and (b),I the licensee may use

,i E for medical use any byproduct materiaU of rea~ gent kit for which the Food and Drug i f' Administration has accepted a " Noti ^c'e of Claimed Investigational Exemption for a g Drug" (IND). h' ^ i q

17. The licensee may transport licensed material in accordance with the provisions of W

4; 10 CFR 71, " Packaging and Transportation of Radioactive Material." Mi g, g"i 18. If only a single radionuclide specified,in N REG 0767, is possessed, the possession ii g limit is the quantity specified in Schedule d Limitino Possession Limits, NUREG- ! l q 0767. If two or more radionuclides are possessed, the possession limit for each is !-l i determined as follows: the sum of the quotients of the quantities possessed divided ! l 5 by the quantities of those radionuclides specified in the Schedule d limitino i j i

1. g Possession Limits, NUREG-0767 shall not exceed unity.

j l qi l f19. The licensee is authorized to hold radioactive material with a physical half-life of ' l 4 less than 90 days for decay-in-storage before disposal in ordinary trash provided: l11 8 J1 A. Radioactive waste to be disposed of in this manner shall be held for decay a J l minimum of 10 half-lives. j i 8 E i lIl t 4 ,11 >i N ( i t r i 1; h B R i !s.zar.z#1'rrassTMMsWETXT282ECT T2iRr.TmT.TmEsramr.ar.Taf.MTrXTmTpMTI t m + - - - - -

p,w. EXT:mcTr:itTra.ms - an-xwnTIrzwxTA "xw.ma..msITi q g sac rorm 374A U. S. N AR REGU8.ATORY CpMMISSION I;I g M *3 PAGE OF PAGE5 Ucense number g 08-01738-02 'I ( MATERIALS LICENSE lf> 3 g , g,,, ( SUPPLEMENTARY SHEET t 030-01317 tf Amendment No. 62 f (19. continued) CONDITIONS h B. Before disposal as normal waste, radioactive waste shall be surveyed to k t f determine that its radioactivity cannot be distinguished from background. All radiation labels shall be removed or obliterated. l C. Generator columns shall be segregated so that they may be monitored separately lp to ensure decay to background levels prior to disposal. 20. Except as specifically provided otherwise in this license, the licensee shall conduct h' its program in accordance with the statements, representations, and procedures contained in the documents, including any enclosures, listed below. The Nuclear Regulatory Commission's regulations shall govern unless the sti.^ements, representations and procedures in the licensee's application mi correspondence are more restrictive than the regulations. f;, t A. Application dated July 18, 1979 l B. Letter dated January 13, 1984 C. Letter dated May 8, 1987' D. Letter dated March 16, 1988 { E. Letter dated March 28, 1988 9 F. Application dated August 5, 1988 l G. Letter dated September.23, 1988 i H. Letter dated July 28, 1989 1. Letter dated September.12,1989 ), l J. Letter dated January-19, 1990 K. Letter dated July 16, 1990 L. Letter dated March 15, 1991 M. Letter dated July 11, 1991 i l N. Letter dated April 8,1992 } 0. Letter dated August 4, 1992 l l P. Letter dated November 24, 1992 4 i J W \\ ) i i l l l For the U.S. Nuclear Regulatory Commission yl APR 151993 odoiner signed ey: W p.m.ta a. sene.r.on A 4 Date By l l Nuclear Materials Safety Branch l g Region I il g King of Prussia, Pennsylvania 19406 R

1. XJXvs varJXt TXpifffMM.wEff?MirsI.T2irmTEstif.TsTXTm

~ - ~ ~ ~

O i I NOTE TO DMB: t TIIE ATTACIIED DOCUMENTS ARE TO BE PROCESSED AS ONE MATERIALS LICENSING PACKAGE. LICENSE NUMBER: 8$-6/73IO DOCKET NUMBER: J :? 6 d'i/ 7 CONTROL NUMBER: // N '72 i TIIIS SIIEET MAY BE DISCARDED AFTER PROCESSING. l TIIANK YOU! 1 l 1 1.10ng3 1 pLe

0 0 i i I APR 151993 1 i i License No. 08-01738-0' Docket No. 030-01317 Control No. I16472 Depanment of the Army ATTN: Colonel Peter H. Myers DASG-PSP-E 5109 Leesburg Pike Falls Church, Virginia 22041-3258 1 l

Dear Colonel Myers:

Please find enclosed an amendment to your NRC Material License. Please review the enclosed document carefully and be sure that you understand all ccmditions. l If there are any errors or questions, please notify the Region I Material Licensing Section, (215) 337-5093, so that we can pmvide appropriate corrections and answers. Please be advised that you must conduct your program involving licensed radioactive j materials in accordance with the conditions of your NRC license, representations made in your license application, and NRC regulations. In panicular, please note the items in the enclosed, " Requirements for Materials Licensees." Since serious consequences to employees and the public can result fmm failure to comply with NRC requirements, the NRC expects licensees to pay meticulous attention to detail and to achieve the high standard of compliance which the NRC expects of its licensees. You will be periodically inspected by NRC. A fee may be charged for mspections m accordance with 10 CFR Pan 170. Failme to conduct your program safely and in accordance with NRC regulations, license conditions, and representations made in your l license application and supplemental correspondence with NRC will result in prompt and vigorous enforcement action against you. This could include issuance of a notice of violation, or in case of serious violations, an imposition of a civil penalty or an onler suspending, modifying or revoking your license as specified in the General Policy and Procedures for NRC Enforcement Actions,10 CFR Pan 2, Appendix C. OFFICIAL RECORD COPY - G:\\WPS\\MLTR\\IA801738.02 - 04/05/93 ML 10 i

O O Department of the Army We wish you success in operating a safe and effective licensed program.

Sincemly, Original Signed By:

Pamela J. Henderson l 1 Pamela J. Henderson 1 Nuclear Materials Safety Branch Division of Radiation Safety and Safeguards

Enclosures:

1. Amendment No. 62

2. Requirements for Materials Licensees 1

3. Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Tennination of Licenses for Byproduct, Soume, or Special Nuclear Material cc:

Walter Reed Anny Medical Center ATTN: Radiation Safety Officer Health Physics Office 2681 Linden I2ne Silver Spring, Maryland 20910 i D .RI Henderson/mlb 4/11/93 OFFICIAL RECORD COPY - G:\\WPS\\MLTR\\IA801738.02 - 04/05/93 l

i O O we l . gg. DEPARTMENT OF THE ARMY g.7 g I ) WALTER REED ARMY MEDICAL CENTER g' hg WASHINGTON, DC 20307-5001 v-R EPLY T O ^" N'" on 24 November 1992 r f Health Physics Office United States Nucleat Regulatory Commission Attention: Chief, Medical Licensing Section Division of Radiation Safety and Safeguards 475 Allendale Road King of Prussia, Pennsylvania 19406-1415

Dear Ms. Jenny M. Johansen:

I We provide the following information in reference to Mail Control No. 116472 and in response to your memo, dated 16 November [ 1992, requesting additional information concerning our dedicated iodine-131 therapy room. As a matter of standing operating procedure, the dedicated therapy room, Room 7437, remains closed and locked when there are no iodine therapies. Only the Health Physics Office possesses a key to that room. Decontamination limits for this room vill be the restricted area action limits established in NRC Regulatory Guide 8.23, " Radiation Safety in Medical Institutions". Health Physics i Office personnel will decontaminate the room below this level of removable contamination prior to admittance of an iodine-131 radiation therapy patient into Room 7437. We hope that this information will satisfy your questions and permit you to grant our exemption to 10 CFR 35.315(a) (7). We i l appreciate your prompt attention to this matter. Your point of contact for this matter is the undersigned at (301)-427-5104/5107. Sincerely, ,N / ARTHQEVG. SA AN Lieutenant Colonel, US Army Health Physics Officer //6 y-7L OPPICIAL liECOllD COPY ML 12 1,gy 3 g 1992 i

O O. ~ I h NOV 161992 i l License No. 08-01738-02 Docket No. 030-01317 4 Control No. I16472 Department of the Army ATTN: Lieutenant Commander Roy D. Quick, Jr. Executive Officer i Walter Reed Army Medical Center Washington, D.C. 20307-5001

Dear Lieutenant Commander Quick:

i i This is in reference to your request in a letter dated April 8,1992 to amend License i No. 08-01738-02. In order to continue our review, we need the following additional l information: i Your request to receive an exemption to 10 CFR 35.315(a)(7), may be granted at such time as you provide the additional commitments /information described in I through 3 below. Please confirm / provide the following: i 1. The door to the contaminated therapy room will remain closed and locked when the room is unoccupied. l 2. The access to the unoccupied and locked room will be under the contml of the Health Physics Office (HPO) at all times and can only be opened by HPO personnel. 3. The dedicated therapy room must be decontaminated, prior to use by any other therapy patient, by one of two methods described below (a or b): .l a. Decontaminate based on the restricted area action level for removable surface contamination of 2,200 dpm/ square centimeter as described in Regulatory j Guide 8.23, " Radiation Safety Surveys at Medical Institutions". j l b. Decontaminate based upon action levels determined to meet the following j critena. i. No primary radiation protection standards will be exceeded (personal dose, member of the public dose or environmental release limits.); an_d i E i OFFICIA.L RECORD COPY - G:\\WPS\\DLTR\\D423 - 11/13/92 -{ MD 10 i ) t m

A A Depanment of the Army ii. The action levels are determined to be ALARA based upon consideration of worker, environmental, and public exposures. Submit a description of the procedures to be followed to determine these criteria are m et. We will continue our review upon receipt of this infonnation. Please reply in duplicate to my attention at the Region I office and refer to hiail Control No. I16472. The reviewer for this licensing action is Pamela Henderson. If you have any technical questions mgarding this deGeiency letter please call the reviewer at (215) 337-6952. If we do not receive a reply trom you within 30 calendar days from the date of this letter, we shall assume that you do not wish to pursue your application. Sincerely, ^ a n,i E!gned Ey- . nc.cus E. Tham;3cn Jenny hi. Johansen, Chief Medical Licensing Section Division of Radiation Safety and Safeguards

Enclosure:

Regulatory Guide 8.23 bec: Depanment of the Amiy Walter Reed Army Medical Center ATTN: Radiation Safety OfGeer Health Physics Office 2681 Linden Lane Silver Spring, Maryland 20910 0 Y DRSS:RNag [I J DRSS:RI Henderson/Pam;ge Johansen / 11/'3/92 11//6/92 OFFICIAL RECORD COPY - G:\\WPS\\DLTR\\D423 - 11/13/92

( %jo. O o 3 UNITED STATES 8 NUCLEAR REGULATORY COMMISSION y g gg g C W ASH 1NGTON, D. C. 20555 s I

x. 7

} SEP 2 41992 MEMORANDUM FOR: Ronald R. Bellamy, Chief Nuclear Materials Safety and Safeguards Branch, RI FROM: John E. Glenn, Chief Medical, Academic, and Commercial Use Safety Branch Division of Industrial and Medical Nuclear Safety, NMSS

SUBJECT:

TECHNICAL ASSISTANCE REQUEST DATED JUNE 10, 1992, RE: AN AMENDMENT REQUEST FROM WALTER REED ARMY MEDICAL CENTER, WASHINGTON, DC, LICENSE NO. 08-01738-02 (CONTROL NO. 116472) l This memorandum responds to a technical assistance request (TAR) dated June 10, I 1992 (enclosed), regarding an amendment request from the Walter Reed Army Medical Center, Washington, DC. In a letter dated April 8,1992, the licensee requested an exception to 10 CFR 35.315(a)(7) to allow dedication of a single patient room for radiopharmaceutical therapies without being required to i decontaminate to the levels required for unrestricted occupancy and assignment to a non-therapy patient. It is our understanding that the licensee does survey and decontaminate the l patient room after release of each therapy patient, but restricts the room for i use only by iodine therapy patients. The licensee therefore requests relief from the requirement of decontaminating the room to the level required to release it as an unrestricted area. If granted this practice would require an exemption from the requirements of 10 CFP,35.315(a)(7) because the regulation i does not anticipate subsequent use of the room by therapy patients, and the required decontamination level of 200 disintegrations per minute (dpm) per 100 centimeters squared (cm) is for release of the room as an unrestricted i area. In the letter dated April 8,1992, the licensee submitted procedures to ensure the safety of facility personnel who frequent the vicinity of a dedicated therapy patient room. 1. The licensee states that the door to the contaminate' therapy room will remain closed and locked when the room is unoccupied. 2. The licensee states that access to the unoccupied and locked room will be under the control of the Health Physics Office (HPO) at all times and can only be opened by HPO personnel. 3. The licensee should be required to decontaminate the dedicated therapy room, prior to use by any other therapy patient, to the restricted area action level for removable surface contamination of 2,200 dpm/100 cm as l described in Regulatory Guide 8.23, " Radiation Safety Surveys at Medical Institutions", or the licensee may be approved to decontaminate based exFICIAI, RECORD COPY h Ig //6 A ffst.kr t_nf ocT, a2.,It1L

t O O t l Mr. Ronald R. Bellamy l l upon action levels determined to meet the following criteria:

a. IJo primary radiation protection standards will be exceeded f

(personal dose, member of the public dose or environmental release limits.); and

b. The action levels are determined to be ALARA based upon a i

consideration of worker, environmental, and public exposures. I The licensee must describe the procedures to be followed to determine [ these criteria are met. i In summary, the licensee's request for an exemption '(to be provided by a f license amendment) from the requirements in 10 CFR 35.315(a)(7) may ba granted at such time as the licensee provides the additional commitments including the t i decontamination level described in item 3 above. Any questions regarding this information should be directed to Robert Ayres of [ this staff at (301) 504-3423. j i s i / I [/JohnE.Glenn, Chief Medical, Academic, and Commercial Use Safety Branch Division of Industrial and i Medical fluclear Safety, NMSS

Enclosure:

j l TAR dtd 6/10/92 i i I 1 I ^ i 1 t { l l f

i JEST FOR TECHNICAL ASSISTANCE O l DATE: 6/10/92 i TO: John E. Glenn , Chief, Medical, Academic, and Commercial .pgg Use Safety Branch, NM55 FROM: Ronald R. Bellamy Iffl . Chief, Nuclear Materials Safety and Safeguards Branch, Region I 08-01738-02 LICENSEE: Walter Reed luTay Medical Center LICENSE NO.: X Control No. 116472 (enclosed) Letter dated April 8, 1992 (enclosed) X 1 Suggested change in licensing procedure (enclosed) l Other (see remarks) Problem / Issue: Walter Reed Army Medical Center (WRNC) is requesting an exemption frun 10 CFR 35.315(a) (7) strich requires that for each patient receiving radiopharmaceutical i therapy and hospitalized, a (Continued on attached sheet) i 4 Action Required: Alternatives Considered: Recommenced Alternative: on - na ehne thie. owmntim te <Tranted with the ra tricticr ctat M ir + c4-,n++n-anena n~-il 8.1992. This letter should be a tie down condition in their license. Remarks: Regional Reviewer: Pamla Henderson Reviewer Code: K-7 Reviewer Phone No. : PPS 346-6952 REV. 8/90

I l 6 ) e i 1 REQUEST FOR TECHNICAL ASSISTANCE Walter Reed Army Medical Center Problem / Issue continued: I licensee shall survey the patient's room and private sanitary facility for removable contamination l with a mdiation detection survey instrument before assigning another patient to the room. The room must not be reassigned until removable contamination is less than 200 disintegrations per minute per 100 square centimeters. WRAMC states that they average thirty iodine therapies per year and have a dedicated room which is assigned only to iodine therapy patients. Before reassigning the mom to another iodine patient, their Health Physics Office personnel clean and disinfect it. The room remains locked until needed for an iodine therapy and may only be opened by health physics personnel. ) i

( O o 030 o/317 DEPARTMENT OF THE ARMY p Y .V ALTER REED A RMY MECICAL.'DITER [ WASHINGTON. D C. 20307 5001 ( ) U W fm or HSHL-HP (385-11m) 8 Apr 92 i MEMORANDUM THRU HQDA (SGPS-PSP-E), 5109 Leesburg Pike, Falls l Church, VA 22041-3258 FOR US Nuclear Regulatory Commission, Region I, Nuclear Material Safety Section A, 475 Allendale Road, King of Prussia, PA 19406-1415 i

SUBJECT:

Application for Exemption to 10 CFR 35.315(a)7 J 1. Request that Walter Reed Army Medical Center (WRAMC), NRC License No. 08-01738-02, be granted exemption frc= the provisions i of 10 CFR 35.315 (a) 7. 2. WRAMC averages thirty iodine therapies per year and has a L dedicated room wnich is assigned only to lodine therapy patients. f lkgt-I Sercre reassigning the room to another iodine therapy patient, Health Physics Office (HPO) personnel clean and disinfect it. The i rcom remains locked until needed. for an iodine therapy and may only be opened by HPO personnel. l Although ensuring a maximum removable room contamination level i 3. of 200 dpm/cm is appropriate for a room that may be utilized by 2 the general public, it does not seem necessary for a room that is solely used by patients that have just received 150 mci of) radiciodine and well trained radiation workers. / i 4. Also, Condition No.5 of the WRAMC authorization procedures has been. modified to delete addresses for USAMRIID and Andrew Rader Army Clinic; to change the Health Physics Office mailing address to .he recently assigned street address; and to include the Nuclear 6 Medicine Clinic as a receipt point for radiopharmaceutical shipments. (Enclosure) I fll:,N 5. Nuclear Medicine has been approved by the WRAMC Radiation Centrol Committee to receive radiopharmaceuticals directly from local pharmacies for more timely and cost ef fective handling of this material. Nuclear Medicine will process all incoming shipments in accordance with Regulatory Guide 10.8 and forward inventory records to the Health Physics Office. w mm y, p r, 7. p Ue w e, 1 "SECTION COPT APR 0 1 ine

m___ i HSHL-HP Application for Exe=ption to 10 CFR 35.315(a)7 SUBJ ECT: FOR THE CO! GANDER: ~ )__ / ); a / c l ROY QUICK, JR. l Encl as . LTC, MS Executive Officer Copy Furnished HSCL-P, Fort Sam Commander, US Army Health Services Command, ATTN: Houston, TX 78234-6000

o o i HEALTH PHYSICS WALTER REED ARMY MEDICAL CENTER Washington, D.C. 20307-5001 CONDITION NO. 5 FOR RADIOACTIVE MATERIAL AUTHORIZATIONS ? PROCEDURES FOR ORDERING, RECEIVING AND SAFELY OPENING PACKAGES CONTAINING RADIOACTIVE MATERIAL i Radioactive material for Walter Reed Army Medical 1. GENERAL. Center (WRAMC) and tenant activities will be ordered, received and secured in accordance with US Army Regulations, Title 10, uode of Federal Regulations, and the provisions of WRAMC's Nuclear Regulatory Commission License. 7 PRINCIPAL USER'S RESPONSIBILITIES. 2. WRAMC Principal Users are responsible for ordering and a. receiving radioactive material in accordance with the instructions outlined below. 3 A Principal User may procure only those radioisotopes b. currently authorized for their use by the WRAMC Radiation Control subject to the limitations of their authorization. Committee, Unless specified prior arrangements have been made with c. the Health Physics Officer,the maximum quantity which may be ordered at any one time is limited by the maximum activity of radioisotope which the User is authorized to possess less that of activity the User will have on hand at the time the thd amount new order is received. Specific prior approval of the Health Physics Office d. shall be required before receiving and/or transferring gifts containing radioactive material. This procedure applies to those All instances where normal supply channels are not utilized. gifts will be delivered to the Health Physics Office unless alternate arrangements are specifically approved by the Health l Physics Office. 3. CRDERING PROCEDUPES. The Principal User shall submit a completed Purchase a. Request through normal supply channels for procurement of all i radioactive materials. r 3 REVISION 3, effective 6 April 1992 i

O CONDITION NO. 5 FOR RADIOACTIVE MATERIAL AUTHORIZATION (PROCEDURES FOR ORDERING. RECEIVING AND SAFELY OPENING PACKAGES CONTAINING RADIOACTIVE MATERIAL) b. In addition to the information required by WRAMC Procurement Regulations, each purchase request shall contain the following: (1) Radionuclide, chemical form, and total activity (Activity is given as microcuries (Uci), millicuries (Mci), or curies (Ci) ; for natural radioactive materials microgram (ug), milligram (mg), gram (g), or kilogram (kg) may be used. (2) This notice will be typed after the item description: RADIOACTIVE MATERIAL NOTIFY HEALTH PHYSICS OFFICE PRIOR TO PLACING ORDER (TELEPHONE NO. (301) 427-5104) (3) The WRAMC Radioactive Material Authorization .. umber will be indicated in the " Attention Line" of the " Ship To" address. (4) Date required or delivery date. (5) The proper shipping address for any radioactive material not specifically exempted by the Health Physics Office (HPO) is: Health Physics Office Bldg 188, 2681 Linden Lane Forest Glen Section Walter Reed Army Medical Center ATTN: Authorization No. Silver Spring, MD 20910 (6) Two specific approved exemptions are: (a) Army Medical Laboratory, Ft. Meade, MD: Radiation Protection Officer Army Medical Laboratory Bldg 2490 Fort Meade, Maryland 20755 2

~ O M ___ a CONDITION NO. 5 FOR RADIOACTIVE MATERIAL AUTHORIZATION (PROCEDURES FOR ORDERING. RECEIVING AND SAFELY OPENING PACKAGES CCNTAINING RADIOACTIVE MATERIAL) (b) Radiopharmaceuticals for WRAMC Nuclear Medicine Clinic: Walter Reed Ar=y Medical Center Nuclear Pharmacy Bldg 2, Room 7A14 Washington, D.C. 20307-5001 4. PECEIVING PROCEDURES. a. All incoming shipments of radioactive material to the Health Physics Office will be received by the Health Physics Office during duty hours, or by the Military Police, WRAMC Forest Glen Section during non-duty hours. Shipments to Fort Meade, or the WRAMC Nuclear Medicine Clinic will be delivered to the address shown in paragraph 3. The Health Physics Office must be notified immediately of any shipment delivered to an unapproved address. b. All incoming packages of radioactive material will be examined for damage immediately upon receipt. Any packages that appear to be wet, punctured, crushed, or otherwise damaged will be considered to be contaminated, until it can be determined that they are not. Incoming radioactive material shipments must be c. centinuously secured against unauthorized removal and the radiation levels adjacent to the secured storage area may not exceed 0.5 mR/hr. 5. SHIPMENT MONITORING & DELIVERY TO AUTHORIZED RECIPIENTS. All shipments of radicactive material must be inspected a. to insure that the shipment does not exceed the possession limits of the Authorization under which it is ordered. Unauthorized shipments will be returned to the vendor when possible, disposed of as radioactive waste, or held by the Health Physics Office until the Principal User obtains an amended Radioactive Material Authorization allowing receipt of the material. Unauthorized shipments will not be held by Health Physics for more than ninety (90) days. b. Shipments will be Delivered to Principal Users by the H,ealth Physics Office after monitoring procedures have been accomplished. 3

.~ ~ O o CONDITION NO. 5 FOR RADIOACTIVE MATERIAL AUTHORIZATION (PROCEDURES FOR ORDERING. RECEIVING AND SAFELY OPENING PACKAGES CONTAINING RADIOACTIVE MATERIAL) I 6. FINAL SOURCE CONTAINER CHECK. The Principal User-is responsible for making a final check of the. radioactive materials

• source container after it is delivered by the Health Physics Office.

This check will follow the steps outlined below: i a. Put on gloves. j b. Open outer package (following manufacturer's directions, if supplied) and remove packing slip. Open inner package and verify that the contents are as listed on the packing slip. 4 c. Check integrity of source container, inspecting for breakage of seals or vials, loss of liquid, discoloration of -j packaging material, etc. l d. Before disposing of clean outer packaging ensure that any " radioactive" labels or statements have been defaced or removed. i -t i J l -i 3 - i 1 4 4 116472

• SECTION COPY" i

~

O OESTFORTECHNICALASSISTANCEO /- L DATE: 6/10/92 TO: John E. Glenn t , Chief, Medical, Acacemic, and Commercial j g Use Safety Branch, NM55 FROM: Ronald R. Bellamy NIO, Chief, Nuclear Materials Safety and Safeguarcs Branch, Region I LICENSEE: Walter Reed Atry Medical Center LICENSE NO.: 08-01738-02 X _ Control No. 116472 (enclosed) ? X Letter dated April 8,1992 (enclosea) Suggested change in licensing procedure (enclosed) ) Other (see remarks) Problem / Issue: Walter Reed Army Medical Center 0@RC) is requesting an exemption frcra 10 CFR 35.315(a) (7) which requires that for each patient receiving radiopharmaceutical therapy and hosoitalized, a (Continued on attached sheet) i Action Requirea: i i I I Alternatives Considered; t i I i 6 Recommenced Alternative: rn 4 +b + +kie ov M irn he cranted with the rcnriction: -t-t=d in a + 1r++r-a,+M nmil R. 1992. fhis letter should be I i a tie dcun condition in their license. Remarks: l i e Regional Reviewer: pa~ela Henderson 4 Reviewer Code: K-7 Reviewer Phone No.: TTS 346-6952 1 1 i REV. 8/90 ,, OFFICIAL RECORD COPY m 10

O o i i REQUEST FOR TECHNICAL ASSISTANCE i I Walter Reed Army Medical Center i Problem / Issue continued: i licensee shall survey the patient's room and private sanitary facility for removable contamination l i with a radiation detection survey instmment before assigning another patient to the room. The i room must not be reassigned until removable contamination is less than 200 disintegrations per f minute per 100 square centimeters. WRAMC states that they average thiny iodine therapies per year and have a dedicated room which is assigned only to iodine therapy patients. Before reassigning the room to another iodine patient, their Health Physics Office personnel clean and disinfect it. The room remains locked until needed for an iodine therapy and may only be j opened by health physics personnel. i l \\ f i l l l 1 l I

O a. ~ ogo od/7 i DEPARTMENT OF THE ARMY t y, ,f' WALTER REED ARMY VECICAL CNT" j WASHINGTON, O C. 20307 5001 C 7 40** OF HSHL-HP (385-11m) 8 Apr 92 MEMORANDUM THRU HQDA (SGPS-PSP-E), 5109 Leesburg Pike, Falls l Church, VA 22041-3258 FOR US Nuclear Regulatorv Commission, Region I, Nuclear Material j Safety Section A, 475 Allendale Road, King of Prussia, PA 19406-1415

SUBJECT:

Application for Exemption to 10 CFR 35.315(a)7 y 1. Request that Walter Reed Army Medical Center (WRAMC), NRC License No. 08-01738-02, be granted exe=ption from the provisions [ of 10 CFR 35.315 (a) 7. 3. WRAMC averages thirty iodine therapies per year and has a [ dedicated room wnich is assigned only to lodine therapy patients. f' l k g t,- l Eefore reassigning the room to another iodine therapy patient, j Health Physics Office (HPO) personnel clean and disinfect it. The i rocm remains locked until needed for an iodine therapy and ray only ) be opened by HPO personnel. i 3. Although ensuring a maximum removable room contamination level c of 200 dpm/cm is appropriate for a room that may be utilized by 2 the general public, it does not seem necessary for a room that-is solely used by patients that have just received 150 mci of) radiciodine and well trained radiation workers. / 4. Also, Condition No.5 of the WRAMC authorization procedures has 1 been. modified to delete addresses for USAMRIID and Andrew Rader Army Clinic; to change the Health Physics Office mailing address to i the recently assigned street address; and to include the Nuclear Medicine Clinic as a receipt point for radiopharmaceutical shipments. (Enclosure) g 5. Nuclear Medicine has been approved by the WRAMC Radiation l control Committee to receive radiopharmaceuticals directly from local pharmacies for more timely and cost ef fective handling of this material. Nuclear Medicine will process all incoming i shipments in accordance with Regulatory Guide 10.8 and forward inventory records to the Health Physics Office. .} j T j "SECTION COPY' . APR 0 0D o

O o i I' l HSHL-HP Application for Exemption to 10 CFR 35.315(a)7

SUBJECT:

i FOR THE COMMANDER: y 7-i , f - t W.P 1 i ROY V. QUICK, JR. Enc 1 LTC, MS as Executive Officer Copy Furnished HSCL-P, Fort Sam l Commander, US Army Health Services Command, ATTN: Houston, TX 78234-6000 l l e i 1 f i i e 1 I t L 4 h t i 6 i

i O o t i r HEALTH PHYSICS WALTER REED ARMY MEDICAL CENTER Washington, D.C. 20307-5001 CONDITION NO. 5 l FOR RADIOACTIVE MATERIAL AUTHORIZATIONS PROCEDURES FOR RECEIVING AND SAFELY OPENING PACKAGES

ORDERING, CONTAINING RADIOACTIVE MATERIAL Radioactive material for Walter Reed Army Medical 1.

GENERAL. and tenant activities will be ordered, received Center (WRAMC) and secured in accordance with US Army Regulations, Title 10, Code of Federal Regulations, and the provisions of WRAMC's Nuclear Regulatory Commission License. PRINCIPAL USER'S RESPONSIBILITIES. 2. WRAMC Principal Users are responsible for ordering and a. receiving radioactive material in accordance with the instructions outlined below. A Principal User may procure only those radioisotopes b. currently authorized for their use by the NRAMC Radiation Control subject to the limitations of their authorization, Committee, Unless specified prior arrangements have been made with c. the Health Physics Officer,the maximum quantity which may be ordered at any one time is limited by the maximum activity of radioisotope which the User is authorized to possess less that the amount of activity the User will have on hand at the time the new order is received. Specific prior approval of the Health Physics Office d. shall be required before receiving and/or transferring gifts containing radioactive material. This procedure applies to those All instances where nor-1 supply channels are not utilized. gifts will be delivered to the Health Physics Office unless alternate arrangements are specifically approved by the Health Physics office. 3. CRDERING PROCEDURES. The Principal User shall submit a completed Purchase ~ a. Request through normal supply channels for procurement of all radioactive materials. REVISION 3, effective 6 April 1992

O ~ v CONDITION NO. 5 FOR RADIOACTIVE MATERIAL AUTHORIZATION (PROCEDURES FOR ORDERING, RECEIVING AND SAFELY OPENING PACKAGES CONTAINING RADIOACTIVE MATERIAL) b. In addition to the information required by WRAMC Procurement Regulations, each purchase request shall contain the following: (1) Radionuclide, chemical form, and total activity (Activity is given as microcuries (Uci), millicuries (Mci), or curies (Ci) ; for natural radioactive materials microgram (ug), milligram (mg), gram (g), or kilogram (kg) may be used. (2) This notice will be typed after the item description: RADIOACTIVE MATERIAL NOTIFY HEALTH PHYSICS OFFICE PRIOR TO PLACING ORDER (TELEPHONE NO. (301) 427-5104) (3) The WRAMC Radioactive Material Authorization Number will be indicated in the " Attention Line" of the " Ship To" address. (4) Date required or delivery date. (5) The proper shipping address for any radioactive material not specifically exempted by the Health Physics Office (HPO) is: Health Physics Office Bldg 188, 2681 Linden Lane Forest Glen Section Walter Reed Army Medical Center ATTN: Authorization No. Silver Spring, MD 20910 (6) Two specific approved exemptions are: (a) Army Medical Laboratory, Ft. Meade, MD: Radiation Protection Officer Army Medical Laboratory Bldg 2490 Fort Meade, Maryland 20755 2

CONDITION NO. 5 FOR RADIOACTIVE MATERIAL AUTHORIZATION (PROCEDURES FOR ORDERING. RECEIVING AND SAFELY OPENING PACKAGES CONTAINING RADIOACTIVE MATERIAL) (b) Radiopharmaceuticals for WRAMC Nuclear Medicine Clinic: Walter Reed Army Medical Center Nuclear Pharmacy Bldg 2, Room 7A14 Washington, D.C. 20307-5001 4. PECEIVING PROCEDURES. All incoming shipments of radioactive material to the a. Health Physics Office will be received by the Health Physics Office during duty hours, or by the Military Police, WRAMC Forest Glen Section during non-duty hours. Shipments to Fort Meade, or the WRAMC Nuclear Medicine Clinic will be delivered to the address shown in paragraph 3. The Health Physics Office must be notified immediately of any shipment delivered to an unapproved address. l b. All incoming packages of radioactive material will be examined for damage immediately upon receipt. Any packages that appear to be wet, punctured, crushed, or otherwise damaged will be considered to be contaminated, until it can be determined that they are not. Incoming radioactive material shipments must be c. continuously secured against unauthorized removal and the l radiation levels adjacent to the secured storage area may not exceed 0.5 mR/hr. 5. SHIPMENT MONITORING & DELIVERY TO AUTHORIZED RECIPIENTS. All shipments of radicactive material must be inspected a. to insure that the shipment does not exceed the possession limits of the Authorization under which it is ordered. Unauthorized shipments will be returned to the vendor when possible, disposed of as radioactive waste, or held by the Health Physics Office until the Principal User obtains an amended Radioactive Material Authorization allowing receipt of the material. Unauthorized shipments will not be held by Health Physics for more than ninety (90) days. i Shipments will be Delivered to Principal Users by the b. H,ealth Physics Office after monitoring procedures have been accomplished. ) 3 l I

(?) v w OCNDITION NO. 5 FOR RADIOACTIVE MATERIAL AUTHORIZATION (PROCEDURES FOR ORDERING. RECEIVING AND SAFELY OPENING PACKAGES CDNTAINING RADIOACTIVE MATERIAL) 6. FINAL SOURCE CONTAINER CHECK. The Principal User is responsible for making a final check of the radioactive materials

• source container after it is delivered by the Health Physics Office.

This check will follow the steps outlined below: a. Put on gloves. b. Open outer package (following manufacturer's directions, if supplied) and remove packing slip. Open inner package and verify that the contents are as listed on the packing slip. c. Check integrity of source container, inspecting for breakage of seals or vials, loss of liquid, discoloration of packaging material, etc. d. Before disposing of clean outer packaging ensure that any " radioactive" labels or statements have been defaced or removed. e 4 116472 SECTION COPT

e apao-CY3/7 1 @ sir %r7cmor , \\- DEPARTMENT OF THE ARMY [ 1 \\. OFFICE OF THE SURGEON GENERAL f [ $109 LEESBURG PIKE g g FALLS CHURCH, VA 22041-3258 g l April 20, 1992 N,/ Preventive Medicine l Consultants Division { } I i US Nuclear Regulatory Commission j Region I i 475 Allendale ( King of Prussia, Pennsylvania 19406 l

Dear Sir:

l l Enclosed are two copies of a request to amend Byproduct i . Material License Number 08-01738-02, Walter Reed Army Medical Center, Washington, DC. Recommend approval. Sincerely, 1 ^f 7g /tA Peter H. 2yers

Colonel,

.S. Army l Radiolo cal Hygiene Consultant 1 Enclosure 1 CF: HSHB-MR-H I l l 116472 ED OFFICIAL RECORD COPY a 24 E 'APR 1819S2 e.oq %d a \\.kS L

O o OM7d&or: f g i DEPARTMENT OF THE ARMY s f l WALTER REED ARMY MEDICAL CENTER WASHIN'iTON, D.C. 20307 5001 / ~ HSHL-HP (385-11m) 8 Apr 92 i t MEMORANDUM THRU HQDA (SGPS-PSP-E), 5109 Leesburg Pike, Falls Church, VA 22041-3258 l FOR US Nuclear Regulatory Commission, Region I, Nuclear Material Safety Section A, 475 Allendale Road, King of Prussia, PA 19406-1415 j l

SUBJECT:

Application for Exemption to 10 CFR 35.315(a)7 i 1. ,.equest that Walter Reed Army Medical Center (WRAMC), NRC License No. 08-01738-02, be granted exemption from the provisions i of 10 CFR 35.315 (a) 7. j 2. WRAMC averages thirty iodine therapies per year and has a dedicated room which is assigned only to iodine therapy patients. -lf ((h7 Before reassigning the room to another iodine therapy patient, Health Physics Office (HPO) personnel clean and disinfect it. The room remains locked until needed for an iodine 'herapy and may only i be opened by HPO personnel. 3. Although ensuring a maximum removable room contamination level f 2 of 200 dpm/cm is appropriate for a room that may be utilized by the general public, it does not seem necessary for a room that is solely used by patients that have just received 150 mci of i radiciodine and well trained radiation workers. l 4. Also, Condition No.5 of the WRAMC authorization procedures has been modified to delete addresses for USAMRIID and Andrew Rader Army Clinic; to change the Health Physics Office mailing address to the recently assigned street address; and to include the Nuclear j Medicine Clinic as a receipt point for. radiopharmaceutical [/57Ij l shipments. (Enclosure) 5. Nuclear Medicine has been approved by the WRAMC Radiation- ,l Control Committee to receive radiopharmaceuticals directly from local pharmacies for more timely and cost effective handling of this material. Nuclear Medicine will process all incoming shipments in accordance with Regulatory Guide 10.8 and forward inventory records to the Health Physics-Office. /@77_ a m,. J

. ~. .- ~ r f . o. o 1 "HSHL-HP

SUBJECT:

Application for Exemption to 10 CFR 35.315(a)7 I t FOR THE COMMANDER: i [ f / I '7 [ Encl RY .' QUICK, JR. as /LTC, MS f e Executive Officer Copy Furnished Commander, US Army Health Services Command, ATTN: HSCL-P, Fort Sam f Houston, TX 78234-6000 [ t I f i f I I I I 4 l t l l 'i t t l

O o HEALTH PHYSICS WALTER REED ARMY MEDICAL CENTER Washington, D.C. 20307-5001 CONDITION NO. 5 FOR RADIOACTIVE MATERIAL AUTHORIZATIONS PROCEDURES FOR ORDERING, RECEIVING AND SAFELY OPENING PACKAGES 4 e CONTAINING RADIOACTIVE MATERIAL 1. GENERAL. Radioactive material for Walter Reed Army Medical Center (WRAMC) and tenant activities will be ordered, received and secured in accordance with US Army Regulations, Title 10, Code of Federal Regulations, and the provisions of WRAMC's Muclear Regulatory Commission License. 2. PRINCIPAL USER'S RESPONSIBILITIES. a. WRAMC Principal Users are responsible for ordering and receiving radioactive material in accordance with the instructions outlined below. b. A Principal User may procure only those radioisotopes currently authorized for their use by the WRAMC Radiation Control Committee, subject to the limitations of their authorization. c. Unless specified prior arrangements have been made with the Health Physics Officer,the maximum quantity which may be ordered at any one time is limited by the maximum activity of that radioisotope which the User is authorized to possess less the amount of activity the User will have on hand at the time the new order is received. d. Specific prior approval of the Health Physics Office shall be required before receiving and/or transferring gifts containing radioactive material. This procedure applies to those instances where normal supply channels are not utilized. All gifts will be delivered to the Health Physics Office unless alternate arrangements are specifically approved by the Health Physics Office. 3. ORDERING PROCEDURES. a. The Principal User shall submit a completed Purchase Request through normal supply channels for procurement of all radioactive materials. REVISION 3, effective 6 April 1992

2 O -+ _ o 4 CONDITION NO. 5 FOR RADIOACTIVE MATERIAL AUTHORIZATION (P'R6CEDURES FOR ORDERING, RECEIVING AND SAFELY OPENING PACKAGES CONTAINING RADIOACTIVE MATERIAL) (b) Radiopharmaceuticals for WRAMC Nuclear Medicine Clinic: Walter Reed Army Medical Center Nuclear Pharmacy Bldg 2, Room 7A14 Washington, D.C. 20307-5001 4. RECEIVING PROCEDURES. a. All incoming shipments of radioactive material to the Health Physics Office will be received by the Health Physics Office during duty hours, or by the Military Police, WRAMC Forest Glen Section during non-duty hours. Shipments to Fort Meade, or the WRAMC Nuclear Medicine Clinic will be delivered to the address shown in paragraph 3. The Health Physics Office must be notified immediately of any shipment delivered to an unapproved address. b. All incoming packages of radioactive material will be examined for damage immediately upon receipt. Any packages that appear to be wet, punctured, crushed, or otherwise damaged will be considered to be contaminated, until it can be determined that they are not. c. Incoming radioactive material shipments must be continuously secured against unauthorized removal and the radiation levels adjacent to the secured storage area may not exceed 0.5 mR/hr. 5. SHIPMENT MONITORING & DELIVERY TO AUTHORIZED RECIPIENTS. a. All shipments of radioactive material must be inspected to insure that the shipment does not exceed the possession limits of the Authorization under which it is ordered. Unauthorized shipments will be returned to the vendor when possible, disposed of as radioactive waste, or held by the Health Physics Office until the Principal User obtains an amended Radioactive Material Authorization allowing receipt of the material. Unauthorized shipments will not be held by Health Physics for more than ninety (90) days, b. Shipments will be Delivered to Principal Users by the Health Physics Office after monitoring procedures have been i accomplished. 3 W OFFICIAL RECORD COPY ML 10 t

gs \\ l (FOR LFM5 USE) j INFORMATION F20H LTS SETdEEN:

---

~~---~~~~~~~--~~

LICENSE F EE MANAGEMENT BRANCH, ARM PROGRAM CODE: 02110 1ND ST AT US CODE: 0 REGION AL LIC ENS ING SECTIONS FEE CATEGORY: Ex 7B 23 2C J EXP. CATE: 19930430 1 FEE COMMENTS: SHIELDING AND RCD USE j DECOM FIN ASSUR REQD: Y l LICENSE FEE TRAN5MITTAL A. REGION I 1. APPLICATION ATTACHED APPLICANT / LICENSEE: ARMY, DEPAPTMENT OC THE i RECEIVE 0 OATE: 720413 00CKET NC: 3001317 CONTROL ND.: 116472 LICENSE NO.: 0E-01733-07 ACTION TYDE: AMENDMENT 2. FEE ATTACHED r A M C U'd T : 'e CHECK N3.: i s

3. COMPENTS i

e SI5NED DATE l v.______.___.__ 3. LICENS E F EE MANAGEMENT BRANCH (CHECK WHEN MILESTONE 03 IS ENTERED I._/) 1. FEE C ATE 50RY AND AMCUNT: 2. CORRECT FEE PAID. APPLICATICN MAY BE PROCESSED FOR: AMENDMENT RENEWAL ,,s, =- m e E -t s j i 3. OTHER I i e SIGNED I 1 3 ATE l -}}