Letter Sequence Other |
---|
|
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance
|
MONTHYEARML1008200192010-03-24024 March 2010 Purdue University, Request for Additional Information, Renewal of Facility Operating License, Financial Qualifications (Tac No. ME1594) Project stage: RAI ML1016201842010-06-0404 June 2010 Purdue University - Request for Additional Information Regarding the Purdue University Reactor License Renewal (Tac No. Me 1594), Responses to RAIs Dated 24 March 2010 Project stage: Response to RAI ML1014604292011-07-0606 July 2011 Purdue University - 30 Day Request for Additional Information Regarding the PUR-1 License Renewal Project stage: RAI ML1034001152011-07-0808 July 2011 Purdue University - 60 Day Request for Additional Information Regarding the PUR-1 License Renewal Project stage: RAI ML1117906492011-08-11011 August 2011 Purdue University, Letter to Licensee, Notice of Acceptance for Docketing and Opportunity to Provide Written Comments And/Or Request a Hearing and Order Imposing Procedures for Access to SGI and SUNSI License Renewal (Tac ME1594) Project stage: Acceptance Review ML1123719362011-08-23023 August 2011 Purdue University - E-mail from J. Jenkins, Purdue to D. Hardesty NRC Project Manager Request for an Extension of Time to Respond to NRC Request for Additional Information Project stage: Request ML1133604702011-11-0404 November 2011 Purdue University - E-mail from J. Jenkins, Purdue to C. Montgomery, NRC Project Manager, Request for an Extension to Respond to NRC Request for Additional Information (30-Day) Dated July 6, 2011 (Tac No. ME1594) Project stage: Request ML11320A2872011-11-15015 November 2011 Response to Request for Additional Information Regarding the Purdue University Reactor License Renewal (TAC ME1594), Response to RAIs Dated 6 July 2011 (ML101460429) Project stage: Response to RAI ML1133604912011-12-28028 December 2011 Purdue University - Approval of Request for an Extension of Time to Respond to NRC Request for Additional Information (Tac No. ME1594) Project stage: RAI ML12006A1932012-01-0404 January 2012 Purdue University - Request for Additional Information Regarding the License Renewal, Responses to RAIs Dated 6 July 2011 Project stage: Response to RAI ML1200500042012-01-0404 January 2012 Purdue University - E-mail from J. Jenkins, Purdue to C. Montgomery, NRC Project Manager Licensee Requesting Extension to Respond to NRC Request for Additional Information Dated July 8, 2011 and July 14, 2011 (Tac No. ME1594) Project stage: Request ML12031A2232012-01-30030 January 2012 Purdue University - Responses to the Request for Additional Information Regarding the Purdue University Reactor License Renewal Dated July 6, 2011 Project stage: Request ML1209005712012-03-26026 March 2012 Purdue University License Renewal -- Renewal for Additional Time to Respond to the 60 and 90 Day Requests for Additional Information (Rais) Until January 31, 2012 Project stage: Other ML1213606312012-05-11011 May 2012 Email - Purdue University License Renewal-Submission Schedule for Request for Additional Time to Respond to the 60- and 90-day Requests for Additional Information (RAIs)--Until January 31, 2012 Project stage: Request ML1210301972012-05-29029 May 2012 Purdue University - NRC Approval of Request for Additional Time to Respond to the 60- and 90-day Requests for Additional Information Until January 31, 2013 Project stage: RAI ML12156A3642012-06-0101 June 2012 Request for Additional Information Regarding the Purdue University Reactor License Renewal (TAC ME1594), Responses to RAIs (ML103400115 and ML103400250) Project stage: Response to RAI ML12170B0182012-06-15015 June 2012 Purdue University - Request for Additional Information Regarding the Purdue University Reactor License Renewal (TAC No. ME1594), Responses to RAIs (ML103400115 and ML103400250) Project stage: Response to RAI ML1218500042012-06-29029 June 2012 Purdue University - Request for Additional Information Regarding the Purdue University Reactor License Renewal, Responses to RAIs (ML103400115 and ML103400250) Project stage: Response to RAI ML12201A0702012-07-13013 July 2012 Purdue University - Request for Additional Information Regarding the Purdue University Reactor License Renewal, Response to RAI Project stage: Response to RAI ML12226A4002012-08-11011 August 2012 Purdue University - Response to Request for Additional Information Regarding Purdue University Reactor License Renewal (TAC No. ME1594, Responses to RAIs (ML103400115 and ML103400250) Project stage: Response to RAI ML13101A0442013-04-10010 April 2013 Purdue University - Response to Request Request for Additional Information Regarding the Purdue University Reactor License Renewal Project stage: Request ML14115A2212014-08-29029 August 2014 Purdue University - Request for Additional Information Regarding the Purdue University Reactor License Renewal Application Project stage: RAI ML15210A2872015-07-24024 July 2015 Purdue University - Request for Additional Information Regarding the Purdue University Reactor License Renewal Application (TAC No. ME1594), Responses to Letter Dated August 29, 2014 (ML14115A221). Part 4 of 5 Project stage: Request ML15210A2852015-07-24024 July 2015 Purdue University - Request for Additional Information Regarding the Purdue University Reactor License Renewal Application (TAC No. ME1594), Responses to Letter Dated August 29, 2014 (ML14115A221). Part 3 of 5 Project stage: Request ML15210A2832015-07-24024 July 2015 Purdue University - Request for Additional Information Regarding the Purdue University Reactor License Renewal Application (TAC No. ME1594), Responses to Letter Dated August 29, 2014 (ML14115A221). Part 2 of 5 Project stage: Request ML15210A2882015-07-24024 July 2015 Purdue University - Request for Additional Information Regarding the Purdue University Reactor License Renewal Application (TAC No. ME1594), Responses to Letter Dated August 29, 2014 (ML14115A221). Part 5 of 5 Project stage: Request ML15210A2802015-07-24024 July 2015 Purdue University - Request for Additional Information Regarding the Purdue University Reactor License Renewal Application (TAC No. ME1594), Responses to Letter Dated August 29, 2014 (ML14115A221) Project stage: Request ML15210A2822015-07-24024 July 2015 Purdue University - Request for Additional Information Regarding the Purdue University Reactor License Renewal Application (TAC No. ME1594), Responses to Letter Dated August 29, 2014 (ML14115A221). Part 1 of 5 Project stage: Request ML15349B0432015-12-23023 December 2015 Purdue University Research Reactor - Request for Additional Information Physical Security Plan Review for License Renewal Project stage: RAI ML16047A3822016-01-29029 January 2016 Purdue University - Response to NRC Request for Additional Information Regarding Physical Security Plan Review for License Renewal Project stage: Response to RAI ML16083A2192016-02-26026 February 2016 Purdue University - Re-Submittal Response to NRC Request for Additional Information Regarding Physical Security Plan Review for License Renewal Project stage: Response to RAI ML16102A1192016-03-31031 March 2016 Purdue Univ., Submittal of 2015 Annual Report for PUR-1 Project stage: Request ML16102A1232016-03-31031 March 2016 Purdue Re-Submittal of Response to NRC Request for Additional Information Physical Security Plan Review for License Renewal Project stage: Response to RAI ML16134A1432016-05-0909 May 2016 Purdue University - Second Re-Submittal of Response to NRC Request for Additional Information Regarding Physical Security Plan Review for License Renewal Project stage: Response to RAI ML16193A6812016-07-0707 July 2016 Purdue University School of Nuclear Engineering Notice of ADAMS Document Correction, PUR-1, Docket 50-182, ML16187A371. Technical Specifications, Proposed Amendment 13 Enclosed Project stage: Request ML16207A4262016-07-19019 July 2016 Purdue University Responses to Request for Additional Information Re PUR-1 License Renewal and Power Uprate Project stage: Response to RAI ML16187A3712016-07-25025 July 2016 Purdue University - Request for Additional Information Regarding the Renewal of Facility Operating License No. R-87 for the Purdue University Reactor Project stage: RAI ML16267A4652016-09-19019 September 2016 Purdue University - Response to Request for Additional Information Regarding the Reactor License Renewal Application, Responses to Letter Dated July 25, 2016 Project stage: Response to RAI ML16277A1652016-09-29029 September 2016 Purdue University - Explanation of Technical Specification Changes and Emergency Operator Action Project stage: Other ML16265A6342016-10-21021 October 2016 Purdue University - Notice of Issuance of Environmental Assessment and Finding of No Significant Impact Regarding the Renewal of Facility Operating License No. R-87 (FRN) Project stage: Request ML16265A6322016-10-21021 October 2016 Purdue University Environmental Assessment and Finding of No Significant Impact Regarding Renewal of Facility Operating License No. R-87 for the Purdue University Reactor (Letter) Project stage: Other 2012-06-29
[Table View] |
|
---|
Category:Emergency Preparedness-Emergency Plan Implementing Procedures
MONTHYEARML16277A1652016-09-29029 September 2016 Purdue University - Explanation of Technical Specification Changes and Emergency Operator Action 2016-09-29
[Table view] Category:Letter
MONTHYEARML23268A0752023-09-18018 September 2023 Purdue Univ., Submittal of Revised License Renewal Request ML23227A2462023-08-16016 August 2023 Examination Confirmation Letter No. 50-182/OL-24-01, Purdue University ML23171B0272023-06-13013 June 2023 Purdue Univ., Reply to Notice of Violation in NRC Inspection Report 05000182/2023201 IR 05000182/20232012023-05-23023 May 2023 Purdue University - U.S. Nuclear Regulatory Commission Safety Inspection Report No. 05000182-2023201 and Notice of Violation ML23090A2012023-03-31031 March 2023 Purdue Univ., Submittal of 2022 Annual Report ML22238A2492022-09-0808 September 2022 Examination Confirmation Letter No. 50-182/OL-23-01, Purdue University IR 05000182/20212042021-12-0202 December 2021 Purdue University U.S. Nuclear Regulatory Commission Follow-Up Safety Inspection Report 05000182/2021204 ML21306A1602021-11-11011 November 2021 Examination Confirmation Letter No. 50-182/OL-22-02, Purdue University ML21267A4272021-09-21021 September 2021 Purdue Univ., Reply to Notice of Violation in NRC Special Inspection Report No. 05000182/2021202 ML21267A4052021-09-14014 September 2021 Purdue Univ., Reply to Notice of Violation in NRC Special Inspection Report No. 05000182/2021203 IR 05000182/20212032021-07-29029 July 2021 Purdue Safety HP - Safety Inspection Report No. 05000182/2021203 and Notice of Violation IR 05000182/20212022021-07-28028 July 2021 Purdue University Nuclear Regulatory Commission Security Inspection Report No. 05000182/2021202 (Cover Letter) ML21173A3102021-06-25025 June 2021 Purdue University Additional Training Preformed in Lieu of Annual Operating Test ML21153A4272021-06-24024 June 2021 Examination Confirmation Letter No. 50-182/OL-21-01, Purdue University ML21172A1562021-06-0303 June 2021 Request to Compensate for a Missed Annual Operating Test by Utilizing 10 CFR 55.59(b) for SOP-70830 at Purdue Univ ML21148A1132021-05-0707 May 2021 Update to Facility Personnel at Purdue University Reactor, PUR-1, Docket 50-182 ML21139A1242021-05-0707 May 2021 Update to Facility Personnel at Purdue University Reactor, PUR-1, Docket 50-182 IR 05000182/20212012021-05-0606 May 2021 Purdue University, Routine Safety Inspection 050182/2021201 ML21118A0232021-03-31031 March 2021 Purdue University - Report on Reactor Operations for the Period January 1, 2020 to December 31, 2020 IR 05000182/20202012021-02-16016 February 2021 Purdue University Reactor Notice of Violation and Special Inspection Report 05000182/2020-201 ML21029A0562021-01-21021 January 2021 Purdue University Reactor, Update to Facility Personnel ML21035A0142021-01-0606 January 2021 Response to Apparent Violations in NRC Special Inspection Report 05000182/2020201 ML20336A3242020-12-11011 December 2020 Purdue University - Issuance of Amendment No. 16 to Renewed Facility Operating License No. R-87, for the Purdue University Research Reactor to Modify the Technical Specifications to Allow Startup of the Purdue University Reactor to Calibrat ML20332A0832020-12-0707 December 2020 Purdue University, Special Inspection Report 05000182/2020201 ML20330A2312020-11-27027 November 2020 Purdue University - Acceptance of the Application for a License Amendment Modification of Technical Specifications to Allow Startup of the Purdue University Reactor to Calibrate Nuclear Instrumentation (EPID A11010//L-2020-PPM-0000) ML20337A1042020-11-24024 November 2020 Purdue University Submission of License Amendment Request, PUR-1, Docket 50-182 ML20295A4242020-11-16016 November 2020 Notification of Mailing Address Change Regarding Submittal of Fingerprint Cards ML20311A2642020-11-0303 November 2020 Purdue Univ. School of Nuclear Engineering - Written Conveyance of 14-Day Special Report, PUR-1 ML20045E4522020-02-18018 February 2020 Purdue University - Acknowledgement of Withdrawal of the Application for a License Amendment Request for Management Chain Change ML20038A2872020-02-0606 February 2020 Purdue University - Withdrawal of License Amendment Request, PUR-1, Docket 50-182 - Management Chain ML20017A2632020-01-17017 January 2020 Purdue University, Indiana - Letter Regarding Dean Mung Chiang New Position Assignment as a Science and Technology Adviser to the Secretary of State ML19345F3782019-12-11011 December 2019 Examination Confirmation Letter No. 50-020/OL-20-01, Massachusetts Institute of Technology ML19345F2712019-12-11011 December 2019 Examination Confirmation Letter No. 50-182/OL-20-01, Purdue University IR 05000182/20192022019-10-30030 October 2019 Purdue University U.S. Nuclear Regulatory Commission Safety Inspection Report No. 05000182/2019-202 ML19274C4472019-10-0808 October 2019 Examination Report No. 50-182/OL-19-01, Purdue University ML19142A2722019-05-24024 May 2019 Purdue University - Issuance of Amendment No. 15 Regarding Implementation Date Change for Licensing Amendment No. 14 for Facility Operating License No. R-87 ML19143A3842019-05-21021 May 2019 LAR Implementation Extenstion - PUR1 - 20190521 ML18262A4342019-04-0101 April 2019 Purdue University Transmittal Letter for Issuance of Amendment No. 14 to Renewed Operating License No. R-87 for the Purdue University Research Reactor Digital Instrumentation Control Upgrade IR 05000182/20192012019-03-20020 March 2019 Purdue University - U.S. Nuclear Regulatory Commission Safety Inspection Report No. 05000182/2019-201 ML18282A1912018-10-0505 October 2018 Purdue University - Interlock Language Retention in Technical Specification Submission Supporting License Amendment Request, PUR-1, Docket 50-182 IR 05000182/20184102018-09-26026 September 2018 Purdue University - Transmittal Letter Regarding U.S. Nuclear Regulatory Commission Security-Related Inspection Report No. 05000182/2018-410 ML18263A1572018-09-20020 September 2018 Purdue University - Revisions to Technical Specification Submission Supporting License Amendment Request, PUR-1, Docket 50-182 ML18134A1612018-05-14014 May 2018 Purdue University - Notification of Level 1 Personnel Change ML18116A4462018-04-20020 April 2018 Purdue Univ., Special Report-Event Notification #53321 - Technical Specification 6.7.b.1.c.vi ML18116A4472018-03-30030 March 2018 Purdue Univ., Submittal of 2017 Annual Report ML18061A1392018-03-0202 March 2018 Purdue University - Augmented Request for Additional Information Response for Digital Control and Instrumentation Upgrade License Amendment Request ML17321B0662017-12-20020 December 2017 Purdue University - Regulatory Audit Report for Digital Control and Instrumentation Up-Grade License Amendment Request ML18010A8952017-12-18018 December 2017 Purdue University - Request for Additional Information Response for Digital Control and Instrumentation Upgrade License Amendment Request ML17272A0392017-10-0303 October 2017 Purdue University Supplemental Information Needed for Acceptance of Requested Licensing Action License Amendment Request for Management Chain Change ML17241A0312017-08-28028 August 2017 Submission of License Amendment Request, PUR-1, Docket 50-182-Management Chain Change 2023-09-18
[Table view] |
Text
PURDUE U N I 1/ *E R S I T Y SCHOOL OF NUCLEAR ENGINEERING Document Control Desk US Nuclear Regulatory Commission One White Flint North 11555 Rock.ville Pike Rock.ville, MD 20852 Attn: Ms. Cindy Montgomery, Research and Test Reactors September 29, 2016
Subject:
Explanation of Technical Specification Changes and Emergency Operator Action
Dear Ms. Montgome1y,
This letter contains a brief summary of the changes that have been made to the PUR-1 Technical Specifications in support of the relicensing and power uprate of the facility as well as a note about proposed actions during a radioactive release. The relicensing and power uprate will allow the I facility to expand its research space through a tenfold increase in neutron flux and enhance its teaching mission through the demonstration of more reactor principles. All changes in the first section are to align the definitions with those provided in ANSI/ANI-15.1-2007. Some definitions are omitted or altered to provide a set of terms which are both facility specific, non-redundant, and are used within the body of the document. An example of this change is the defined Power Level. Similarly, the body of the document contains editorial changes intended to improve readability. Throughout the document, some text has been repositioned in an effort to be more clear as to the purpose or role of certain text. An example of this re-alignment is in Section 2.1 which has placed the discussion of Safety limit in the Basis rather than as an opening paragraph. Throughout the document, the change of power is also noted and associated changes in related parameters included. The requested power level scram is at 12.0 k.W rather than the old power level. Specification 3.2.d has been added to require the capability of the pool top radiation monitor to notify off-site personnel of a potential radiation alarm when the facility is unattended. This Technical Specification ensures the dose given to a member of the public remains below the limits as set fortl1 in 10 CFR Part 20. Table I changes are to indicate the value at which a Scram, setback., or interlock shall happen. The change includes tl1e range of values at which the action should occur such as a period of "7 seconds or greater". This change ensures uniform interpretation by the regulator and licensee. Table I also indicates tl1ose setpoints previously not credited for in tl1e Safety Analysis Report. Table II has added a note which indicates and references fue change in 3.2.d. School of Nuclear Engineering . . -* Nuclear Engineering Building
- 400 Central Drive *West Lafayette, IN 47907-2017 (765) 494-5739
- https://engineering.purdue.edu/NE Specification 3.3.d has been edited for several purposes. The first is to remove the requirement of monitoring the pH of the primary coolant. Analysis has shown that monitoring the conductivity of the coolant will indicate abnormal pH levels. A requirement for the water coolant height has been clarified to be while the reactor is operating or, alternatively, to be at a height to keep radiation levels low enough to ensure compliance with 10 CFR Part 20. A water coolant temperature limit has been added to align with the safety analysis. Finally, a clarification has been added which states that the coolant radiation levels shall not exceed those in Appendix B of 10 CFR 20. Specification 3.4.d places a limit on the concentration of Argon-41 being exhausted to the environment. This ensures 10 CFR Part 20 compliance. Specification 3.4 contains statements of "shall" which have been changed from "will". Similar changes exist throughout the document to indicate compulsory action compared to those which are optional. Specification 3.4 also contains some minor clarification statements bringing the language to modern usage standards. Specification 3.5 has removed the limit on temperature of an experiment as that specification can be administratively covered by the facility or would fall under other requirements. Additionally, former language was unclear as to the radioactive content of experiments which could be used. This language has been cleaned and re-written as Specifications 3.5.c and 3.5.f respectively. Specification 3.6 has been added and contains specifications which were formerly located in other portions of the document. Specification 4.1 has been amended to have surveillance periods commensurate with intervals suggested to the facility. Additionally, the requirement to measure worth of rods in the first start-up following a core change has been clarified. Specification 4.2 has been changed to clarify when calibrations must be performed as well as to bring the periodicity to industry standards. Similar changes to intervals were made throughout the document. 4.2.e has been added to give surveillance to requirements in Specification 3 . . Specification 4.3 has included a requirement for the coolant temperature to be recorded in the log book at no interval to exceed four hours when any shim-safety is higher than 6 cm in order to provide surveillance to Specification 3. Specification 4.4 has removed the requirement to inspect representative fuel assemblies as this requirement is located in Section 4.6. Specification 4.5 has been clarified and combined from other sections in the former Technical Specifications to provide uniform interpretation. Specification 4. 7 clarifies dosimetry locations to ensure 10 CFR Part 20 limits are met. The entirety of the Section 5 changes are to better match the facility as currently designed and under which the Safety Analysis. Report has been prepared. This section also contains numerous clarifications of compulsory actions by stating Ilic Specifications as "shall" statements. School of Nuclear Engineering Nuclear Engineering Building
- 400 Central Drive *West Lafayette, IN 47907-2017 (765) 494-5739
- https://engineering.purdue.edu/NE Section 6 was completely re-written to align with the guidance in ANSI/ANS-15.1-2007 and ensure that the administrative controls over the facility ensure safety, are clear in their requirements, and that the line management is well specified. Finally, thorough analysis, it was determined that the dose from an accident to a member of the public would be minimized by leaving the reactor room fan on and venting contaminated reactor room air to the atmosphere where it can disperse to safe levels. This proposal has been changed in the internal Reactor Operator Emergency Procedure guide sheet which is attached to this submission as an example. Should you have any questions or require further information, please don't hesitate to call me at 765-494-5764, or email me at clive@purdue.edu. I hereby certify under penalty of perjury with my signature* below that the information contained in this submission is true and correct to the best of my knowledge. Clive Townsend PURI, Reactor Supervisor Purdue University Attachments: PUR-1 Emergency Procedure Guide cc: Leal1Jamieson, Dean, Purdue University College of Engineering Jim Schweitzer, Purdue University Radiation Safety Officer, CORO Chair Klod Kokini, Interim Head, Purdue School of Nuclear Engineering School of Nuclear Engineering Nuclear Engineering Building* 400 Central Drive* West Lafayette, IN 47907-2017 (765) 494-5739
- https://engineering.purdue.edu/NE EMERGENCY PROCEDURE (911, Cell 765-494-8221) EMERGENCY DIRECTOR As the Reactor operator (RO) you are by definition the Emergency Director (ED). As you are required to call backup in the form of the 'SRO on call', assistant LD, and the LD. They become the ED as they arrive on the scene and relieve the former ED. The ED has ultimate authority over all onsite (Nuclear-Engineering basement lab area) activities and personnel. ED will activate that portion of the organization necessary to* respond to the emergency situation. The ED shall brief arriving responders (other Reactor operations staff, the next or arriving ED, PUPD, PUFD, REM, and etc.). The action to be taken next depends on the nature of the emergency. No procedure can cover all possible situations. 1.) Protect personnel 2.) Protect property and equipment. COMMUNICATION Communication will be by telephone, short wave radio, public address system or word of mouth, as appropriate. The communication signal for facility evacuation is one blast of an evacuation horn. SETBACK BY INSTRUMENTATION If there is an automatic 'setback' by the Reactor instrumentation and the operator recovers without a Scram. The operator will log the event into the log book. Unless standing orders or procedures require otherwise the operator may recover and continue to operate as with a normal run. SCRAM BY INSTRUMENTATION The Reactor will Scram automatically (Trip) when one of the preset safety parameters is exceeded (see 'Setpoint' Table 1 Tech. Spec.). Follow with a manual scram. The annunciator board will indicate the source of the Scram. The time and reason for the Scram must be recorded in the Reactor Log Book. Normal shutdown procedure should be followed after the scram. The operator should make an effort to 'Secure' the Reactor as usual. The SRO on call must be notified. The Reactor may not be restarted after a Scram unless an SRO is present. Consult the flow chart 'Operational Procedure Following a Scram' for guidance in assessment and restarting the Reactor. 'NON -REACTOR SAFETY RELATED EVENT' and SHUTDOWN If there is a 'Non-Reactor Safety Related Event', CIVIL DISTURBANCE, non-Reactor specific BOMB THREAT, INJURY with or without contamination, minor non-Reactor related FIRE, minor non-Reactor related EXPLOSION, or facility or individual CONTAMINATION, the Reactor may be shutdown using 'Gang lower' or Scram to reallocate personnel or due to injuries to a key individual or event escalation. A. Non-Reactor Safety Related Event and Shutdown. The Reactor operator (ED): a.) May 'Gang lower' or Scram the Reactor if necessary. b.) Will log the event in the log book then follow the normal shutdown procedure. c.) If evacuation is necessary, may sound the evacuation horn and/or use word of mouth to notify others. All contaminated articles should be left in the Reactor room. d.) Will notify the SRO on call. e.) Should: Call REM, PUFD, ambulance, and/or PUPD as the situation warrants (911, cell 494-8221). Use the Emergency Roster as necessary. f.) Advise PUPD as necessary. g.) Control access to any spill.
h.) Will monitor all personnel for contamination and determine the necessity of further restriction of movement. Segregate contaminated or potentially contaminated personnel. Record data (readings, dosimeters, make a map as necessary, etc.) as time permits. i.) Will notify the LD. j.) The nature and extent of the accident will be ascertained and necessary action taken. [Use the Emergency Procedure in the Purdue Radiation Safety Manual, or Chemical Hygiene Plan and Hazardous Materials Safety Manual for guidance.] 'NOTIFICATION of UNUSUAL EVENT' and EMERGENCY SHUTDOWN If there is a 'Notification of Unusual Event', ifthe Reactor is not functioning in a safe manner, or in accordance with the procedure of the prescribed experiment, or in case of BOMB threat with possible RADIOLOGICAL RELEASE, FIRE or EXPLOSION in the building with possible REACTOR INVOLVMENT, AIRBORN CONTAMINATION, a RADIOACTIVE SPILL with Reactor involvement, EXPERIMENT FAILURE with Reactor involvement, TORNADO TOUCHDOWN with possible Reactor involvement, NUCLEAR INCIDENT, or other Reactor involved EMERGENCY, RAM alarm, or CAM alarm, the Reactor may be SCRAMMED. Our E-plan states that: 'it (Notification of Unusual Event) may warrant an immediate shutdown of the Reactor or interruption of routine.functions'. As a general rule for Notification of Unusual Event the Reactor would be shutdown. Specifically for Notification of UE: 'Bomb Threat', Fire, and/or Explosion 'the Reactor will be shutdown and all persons evacuated'. For Notification ofUE: 'Tornado' the Reactor will be shutdown and secured, 'then report to a sheltered area'. TO SCRAM THE REACTOR depress the large red Scram button on the annunciator panel or the Scram button just outside the door of the Reactor room. IF THE REACTOR FAILS TO SCRAM or SHUTDOWN open the two containers of BORIC ACID and invert them over the Reactor pool. The boric acid is kept on top of the Reactor console and is plainly marked. SCRAM and EVACUATION B. If airborne contamination is eminent, suspected, or indicated (CAM or RAM alarm). The Reactor operator (ED) shall: a.) Scram the Reactor. b.) Sound the evacuation horn and use word of mouth to notify others. c.) Evacuate the room through the exit involving the least exposure to the spill. All contaminated articles should be left in the Reactor room. d.) Control access to the Reactor room. e.) Verify that all personnel are present. f.) Will monitor all personnel for contamination and determine the necessity of further restriction of movement. Segregate contaminated or potentially contaminated personnel. Record data (readings, dosimeters, make a map as necessary, etc.) as time permits. g.) Notify the SRO on call, RSO, PUPD, and LD. Call PUFD, ambulance, and/or PUPD as the situation warrants (911, cell 494-8221). Use the Emergency Roster as necessary. h.) The nature and extent of the accident will be ascertained and necessary action taken. In all cases, it is up to the Reactor operator (RO)/Emergency Director (ED) to act as the emergency requires. The ED should take more drastic or less drastic action as his/her appraisal of the situation indicates is required. For emergencies not explicitly described here the ED will have to improvise a procedure. The ED should take precautionary and corrective steps to prevent the escalation of the event or to mitigate the consequences thereof. The ED should follow the general guidelines indicated in the procedures discussed here.