ML20205C046

Proposed Tech Specs,Changing Seven Member Safety Committee to Make Reactor Supervisor Voting Member of Safety Committee & Reducing Required Number of Faculty Members on Committee from Five to Four

ML20205C046
Person / Time
Site:	05000157, 05000097
Issue date:	03/23/1999
From:	CORNELL UNIV., ITHACA, NY
To:
Shared Package
ML20205C025	List: ML20205C021 ML20205C035 ML20205C046
References
NUDOCS 9904010063
Download: ML20205C046 (8)

Text

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6.0 Administrative Controls 6.1 Orcanization and Responsibilities of Personnel a ) TheTRIGA Reactor located in the J. Carlton Ward, Jr. Laboratory of Nuclear Engineering shall be an integral part of the Ward Center for Nuclear Sciences of Cornell University.

The reactor organization shall be related to the University structure as shown in Chart L b) The Vice Provost for Physical Sciences and Engineering shall be responsible for the appointment of responsible and competent persons as members of the Ward Center Safety Committee and as Director of Ward Center. In making these appointments, he or she shall consult with the Ward Center Advisory Board.

c) The Ward Laboratory (including but not limited to the TRIGA Reactor) shall be under the supervision of the Center Director, who shall have the overall responsibility for safe, efficient, and competent use of its facilities in conformity with all applicable laws, regulations, terms of facility licenses, and provisions of the Ward Center Safety Committee. He or she shall also have responsibility for maintenance and modification of Laboratory facilities. He or she shall have education and/or experience commensurate with the responsibilities of the position. He or she shall report to the Vice Provost.

d) The Reactor Supervisor shall serve as the deputy of the Center Director in all matters relating to the establishment and enforcement of rules and procedures. He or she should have at least a bachelors degree in a physical science or engineering disciphne, or equivalent knowledge and experience, and shall possess a Senior Reactor Operator's license. He or she shall have had at least two years of reactor operating experience and have a demonstrated competence in supervision. He or she shall be appointed by the

' Center Director with the approvals of the Vice Provost and the Ward Center Safety Committee, and shall report to the Center Director, e) The Responsible Person on Duty shall be responsible for enforcing all applicable rules, procedures, and regulations while he or she is on duty, for ensuring adequate exchange of information between operating personnel when shifts change, and for reporting all malfunctions, accidents, and other potentially hazardous occurrences and situations to the Reactor Supervisor and/or Center Director. Responsible Persons shall possess a Senior Operator's license, shall be appointed by the Center Director with the approval of the Center Safety Comrmttee, and shall report to the Reactor Supervisor.

f) The Reactor Operator shall ba responsible for the safe and proper operation of the reactor, under the direction of the Responsible Person on Duty. Reactor Operators shall possess an Operator's or Senior Operator's license and shall be appointed by the Center Director.

g) The University Radiation Safety Officer (URSO), or his/her deputy, shall (in addition to other duties defined by the Director of Eny'ronmental Health and Safety) be responsible for overseeing the safety of Ward Center operations from the standpoint of radiation protection. He or she shall be appointed by the Director of Environmental Health and Safety with the approval of the University Radiation Safety Committee. He or she shall i report to the Director of Environmental Health and Safety, whose organization is I independent of the Ward Center organization, as shown on Chart L h) The Director of Ward Center, with the approval of the Ward Center Safety Committee, may designate an appropriately qualified member of the Center organization as Ward l 1

I 9904010063 990323 29 PDR ADOCK 05000097 P PDR _

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1 Center Radiation Safety Officer (WCRSO) with duties including those of an intra-Center Radiation Safety Officer. The University Radiation Safety Officer may at his or her discretion, and with the concurrence of the Center Director, authorize the WCRSO to perform some of the specific duties of the URSO at Ward Center.

6.2 Review and Audit a) There will be a Ward Center Safety Committee which shall review TRIGA reactor operations to assure that the reactor facility is operated and used in a manner within the terms of the facility license and consistent with the safety of the public and of persons within the Laboratory.

b) The responsibilities of the Committee include, but are not limited to, the following:

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1. Review and approval of rules, procedures, and proposed Technical Specifications;

2. Review and approval of all proposed changes in the facility that could have a significant effect on safety and of all proposed changes in rules, procedures, and Technical Specifications, in accordance with procedures in Section 6.3;

3. Review and approval of experiments using the reactor in accordance with procedures and criteria in Section 6.4;

4. Determination of whether a proposed change, test, or experiment would constitute an unreviewed safety question or change in the Technical Specifications (Ref.10 CFR 50.59);

5. Review of the operatien and operations records of the facility;

6. Review of abnormal performance of plant equipment and operating anomalies;

7. Review of unusual or abnormal occurrences and incidents which are reportable under 10CFR 20 and 10 CFR 50;

8. Inspection of the facility, review of safety measures, and audit of operations at a frequency not less than once a year; and

9. Approval of appointments of Responsible Persons.

c) The Committee shall be composed of:

1. one or more persons proficient in reactor and nuclear physics,

2. one or more persons proficient in chemistry or chemical engineering,

3. one person proficient in biological effects of radiation, l

4. the Center Director, ex officio, I

5. the University Radiation Safety Officer or his or her deputy, ex officio, and, )

6. a member of the Executive Committee of the Ward Center Advisory Board or his or her  !

deputy, ex officio, and,

7. the Reactor Supervisor, ex officio. j The same individual may serve under more than one category above, but the minimum l membership shall be seven. At least four members shall be faculty members.

d) The Committee shall have a written statement defining its authority and responsibilaies, the subjects within its purview, and other such administrative provisions as are required for its effective functioning. Minutes of ali meetings and records of all formal actions of the Committee shall be kept.

c) The chairman of the Committee shall be elected by the Committee from its members, except that the Center Director or Reactor Supervisor shall not serve as chairman. A quorum shall 30

consist of not less than a majmity of the full Committee and shall include the chairman or

' his or her designee.

f) The Committee shah meet a minimum of three times a year.

6.3 Procedures i

a) Written procedures, reviewed and approved by the Ward Center Safety Committee, shall be followed for the activities listed below. The procedures shall be adequate to assure the safety of the reactor, persons within the Laboratory, and the public, but should not preclude the use of independent judgment and action should the situation require it. The activities  !

are:

1. Startup, operation, and shutdown of the reactor, including (a) startup checkout procedures to test the reactor instrumentation and safety systems,  ;

area monitors, and continuous air monitors, and I l

(b) shutdown procedures to assure that the reactor is secured before operating personnel go off duty.

2. Iastallation or removal of fuel elements, control rods, and other core components that significantly affect reactivity or reactor safety.  ;

3. Preventive or corrective maintenance activities which could have a significant effect I on the safety of the reactor or personnel. l

4. Periodic inspection, testing or calibration of auxiliary systems or instrumentation that relate to reactor operation. l b) Substantive changes in the above procedures shall be made only with the approval of the Center Safety Committee, and shall be issued to the operating personnel in written form.

Temporary changes that do not change the original intent may be made by the Responsible l Person on Duty with the concurrence of the Reactor Supervisor or Center Director. If the two l parties disagree on the change, the change shall not be made. The change and the reasons thereof shall be noted in the log book, and shall be subsequently reviewed by the Center Safety Committee.

c) Determination as to whether a proposed activity in categories (1), (2) and (3) in Section 6.2b above does or does not have a significant safety effect and therefore does or does not require approved written procedures shall require the concurrence of: l

1. the Center Director, and

2. at least one other member of the Center Safety Committee, to be selected for relevant expertise by the Center Director. If the Director and the Committee member disagree, or if in their judgment the case warrants it, the proposal shall be submitted to the full Committee, and

3. the University Radiation Safety Officer, or his or her deputy, who may withhold agreement until approval by the University Radiation Safety Committee is obtained.

Determinations that written procedures are not required shall be subsequently reviewed by the Center Safety Committee. The time at which determinations are rnade, and the review and approval of written procedurce, if required, are carried out, shall be a reasonable interval before the proposed activity is to be undertaken.

d) Determination that a proposed change in the facility does or does not have a significant safety effect and therefor does or does not require review and approval by the full Center 31

Safety Committee shall be made in the same manner as for proposed activities under (c) above.

6.4 Review of Procosals for Experiments ,

a) All proposals for experiments involving the reactor shall be revicwed with respect to safety in accordance with the procedures in (b) below and on the basis of criteria in (c) below.

b) Procedures:

1. The experimenter shall describe the proposed experiment in written form in sufficient detail for consideration of safety aspects. If potentially hazardous operations are involved, proposed procedures and safety measures including pro';ectiva and monitoring equipment rhall be described.

2. If the experimenter is a student, approval by his or her research supervisor is required.

If the experimenter is a staff member, his or her own signature is sufficient.

3. The proposal is then to be submitted to the Center Director for safety review. (In the absence of the Center Director, the Vice Provost may designate another Center Safety Committee member to act.) Safety approval requires the approval of the Center Director and at least one other person selected by him or her from the membership of the Center Safety Committee. If the two individuals agree, approval is granted. If they disagree, or if in their judgment the case warrants it, the proposal will be referred to the full Center Safety Committee.

4. Review and countersignature by the University Radiation Salety Officer or his or her deputy, who shall,if he/she deems it appropriate, indicate on the form that the experiment (or portions thereof) cannot be performed except while he or she is present.

5. The scope of the experiment and the procedures and safety measures as described in the approved proposal, including any amendments dr conditions added by those reviewing and approving it, shall be binding on the experimenter and the operating personnel.

Minor deviations shall be allowed only in the marmer described in Section 6.3b above.

6. Transmission to the Reactor Supervisor for scheduling.

c) Criteria that shall be met before approval can be granted shali inclutt.

1. The experiment must fall within the limitations given in Section 3.8.

2. It must not involve violation of any condition of the facility license or of Federal, State, University, or Center regulations and procedures. The possibility of an unreviewed safety question (10 CFR 50.59) must be examined.

3. In the safety review the basic criterion is that there shall be no hazard to the reactor, personnel or public.

4. Each experiment is reviewed with respect to the following factors:

( (a) pressure change (b) temperature change (c) collapse, implosion, or explosion (d) change of state of sample during irradiation (c) chemical reactions (including corrosion)

(f) leakage of radioactive material (double encapsulation is sometimes required)

(g) radiation levels at d personnel exposure upon remeval of sample (h) internal and external radiation hazards to personnel in proposed operatior.s subsequent to sample removal .

(i) radiation levels in accessible areas during reactor cperation (e.g., for beam experiments)

(j) adequacy of proposed measures to safeguard against accident during experiment 32

(k) adequacy of proposed emergency procedures (if needed) to supplement standard emergency procedures in the event of accident (1) number of reactor operations personnel required (m) number and type of radiation monitors required (n) reactivity effects (normal and accidental)

(o) other relevant factors not included above

5. No explosive material as defined in Title 49, Parts 172 and 173 of the Code of Federal Regulations is permitted within the reactor bay.

6.5 Emercency Plan and Procedures i

An emergency plan shall be established and followed in accordance with NRC regulations. l The plan shall be reviewed and approved by the Center Safety Committee prior to its ]

submission to the NRC. In addition, emergency procedures that have been reviewed and 1 approved by the Center Safety Committee shall be established to cover all foreseeable emergency conditions potentially hazardous to persons within the Laboratory or to the public, including, but not limited to, those involving an uncontrolled reactor excursion or an uncontrolled j release of radioactivity.

6.6 Onerator Recualification An operator requalification program shall be established and followed in accordance with NRC regulations. t 6.7 Physical Security Plan A physical security plan for protection of the reactor plant shall be established and followed in accordance with NRC regulations.

l 6.8 & tion To Be Taken In The Event A Saferv Limit Is Exceeded in the event a safety limit is exceeded a ) The reactor shall be shut down and reactor operation shall not be resumed until authorized by the Director, Division of Reactor Licensing, NRC.

b) An immediate report of the occurrence shall be made to the Chairman of the Center Safety Committee, and reports shall be made to the NRC in accordance with Section 6.11 of these specifications.

c) A report shall be made to include an analysis of the causes and extent of possible resultant damage, efficacy of corrective action, and recommendations for measures to prevent or reduce the probability of recurrence. This report shall be submitted to the Center Safety Committee for review, and a suitable similar report submitted to the NRC when authorization to resume operation of the reactor is sought.

6.9 Action To Be Taken In The Event Of A Reoortable Occurrence a) A reportable occurrence is any of the following conditions:

1. any actual safety system setting less conservative than specified in Section 2.2, Limiting Safety System Settings;

2. eperation in violation of a limiting conditions for operation (Section 3.0);

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3. incidents or conditions that prevented or could have prevented the performance of the intended safety functions of an engineered safety feature or the reactor safety system;

4. release of fission products from the fuel;

5. an uncontrolled or unanticipated change in reactivity greater than 50.50;

6. an observed inadequacy in the implementation of either administrative or procedural controls, such that the inadequacy has caused the existence or development of an unsafe condition in connection with the operation of the reactor;

7. an uncontrolled or unanticipated release of radioactivity.

b) In the event of a reportable occurrence, the following actions sha'l be taken:

1. The reactor shall be shut down at once. The Reactor Supervisor shall be notified and corrective action taken before operations are resumed; the decision to resume shall require approval following the procedures in Section 6.3.

2. A report shall be made to include an analysis of the cause of the occurrence, efficacy of corrective action, and recommendations for measures to prevent or reduce the probability of recurrence. This report shall be submitted to the Center Safety Committee for review.

3. A report shall be submitted to the NRC in accordance with Section 6.11 of these specifications.

6.10 Plant Ooeratinc Records a ) In addition to the requirements of applicable regulations, in 10 CFR 20 and 50, records and logs shall be prepared and retained for a period of at least 5 years for the folle,ving items as a minimum:

1. normal plant operation, including power levels;

2. principal maintenance activities;

3. reportable occurrences; .

4. equipment and component surveillance activities;

5. experiments performed with the reactor;

6. all emergency reactor scrams, including reasons for emergency shutdowns.

o) The following records shall be maintained for the life of the facility:

1. gaseous and liquid radioactive effluents released to the environs;

2. offsite environmental monitoring surveys;

3. fuel inventories and transfers;

4. facility radiation and contamina' ion surveys;

5. radiation exposures for all persevel;

6. updated, corrected, and as-built drawings of the facility.

6.11 Reportine Requirements All written reports shall be sent within the prescribed interval to the United States Nuclear Regulatory Commission, Washington, D.C.,20555, Attn: Document Control Desk, with a copy to the Regional Adruinistrator, Region I.

In addition to the requirements of applicable regulations, and in no way substituting thercior, reports shall be made to the U.S. Nuclear Regulatory Commission (NRC) as follows:

l a) A report within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and telegraph to the NRC Operation Center and Region I, of; i

1. any accidental release of radioactivity above permissible limits in unrestricted areas, whether or not the release resulted in property damage, personal injury, or exposure;

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2. any violation of a safety limit;

3. any reportable occurrences as defined in Section 1.1 of these specificatians.

l b) A report within 10 days in writing to the NRC Operation Center and Region 1 of; I

1. any accidental release of radioactivity above permissible limits in unrestricted areas, I whether or not the release resulted in property damage, personal injury or exposure; the written report (and, to the extent possible, the preliminary telephone and telegraph report) shall describe, analyze, and evaluate safety implications, and outline the corrective measures taken or planned to prevent recui rence of the event;

2. any violation of a safety limit;

3. any reportable occurrence as defined in Section 1.1 of these specifications. J c) A report within 30 days in writing to the Director, Non-Power Reactors and Decommissioning Project Directorate, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555 of;

1. any significant ariation of measured values from a corresponding predicted or previously measured value of safety-connected operating characterisdes occurring during operation of the reactor;

2. any significant change in the transient or accident analysis as described in the FSR.

d) A report within 60 days after criticality of the reactor in writing to the NRC Operation Center and Region I, resulting from a receipt of a new facility license or an amendment to the license authorizing an increase in reactor power level or the installation of a new core, describing the measured values of the operating conditions or characteristics of the reactor under the new conditions.  ;

1 e) A routine report in writing to the U.S. Nuclear Regulatory Commission,. Document Control Desk, Washington, DC 20555 and Region I, within 60 days after completion of the first calendar year of operating and at intervals not to exceed 12 months, thereafter, providing the following information:

1. a brief narrative summary of operating experience (including experiments performed), l changes in facility design, performance characteristics, and operating procedures related to reactor safety occurring during the reporting period; and results of l surveillance tests and inspections; l

2. a tabulation showing the energy generated by the reactor (in megawatt-hours);

3. the number of emergency shutdowns and inadvertent scrams, including the reasons thereof and corrective action,if any, taken;

4. discussion of the major maintenance operations performed during the period, including the effects, if any, on the safe operation of the reactor, and the reasons for any corrective maintenance required;

5. a summary of each change to the facility or procedures, tests, and experiments carned out under the conditions of 10 CFR 50.59;

6. a summary of the nature and amount of radioactive effluents released or discharged to the environs beyond the effective control of the licensee as measured at or before the point of such release or discharge;

7. a description of any environmental surveys performed outside the facility;

8. a summary of radiation exposures received by facility personnel and visitors, including the dates and time of significant exposure, and a brief summary of the results of

. radiation and contamination surveys performed within the facility.

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6. Administrative Controls 6.1 Oreanization and Responsibilities of Personnel a) The Zero Power Reactor, locawd in the J. Carlton Ward, Jr. Laboratory of Nuclear j Engineering, shall be part of the Ward Center for Nuclear Sciences of Cornell University. l The reactor organization shall be related to the University structure as shown in Chart I.

b) The Vice Provost for Physical Sciences and Engineering shall be responsible for the appointment of responsible and competent persons as members of the Ward Center Safety Committee and as Director of 7.ard Center. In making these appointments, he or she shall consult with the Ward Center Advisory Board.

c) The Ward Laboratory (including but not limited to the Zero Power Reactor) shall be under the supervision of the Center Director, who shall have the overall responsibility for safe, efficient, and competent use of its facilities in conformity with all applicable laws, regulations, terms of facility licenses, and providons of the Ward Center Safety Committee. He or she shall also have responsibility for maintenance and modification of Laboratory facilities. He or she shall have education and/or experience commensurate with the responsibilities of the position. He or she shall report to the Vice Provost.

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d) The Reactor Supervisor shall serve as the deputy of the Center Director in all matters relating to the establishment and enforcement of rules and procadures. He or she should have at least a bachelors degree in a physical science or engineering discipline, or  !

equivalent knowledge and experience, and shall possess a Senior Reactor Operator's I license. He or she shall have had at least two years of reactor operating experience and have a demonstrated competence in supervision. He or she shall be appointed by the Center Director with the approvals of the Vice Provost and the Ward Center Safety Committee, and shall report to the Center Director, e) The Responsible Person on Duty shall be responsible for enforcing all applicable rules, procedures, and regulations while he or she is on duty, for ensuring adequate exchange of  ;

information between operating personnel when shifts change, and for reporting all mr.lfunctions, accidents, and other potentially hazardous occurrences and situations to the Reactor Supervisor and/or Center Director. Responsible Persons shall possess a Senior Operator's license, shall be appointed by the Center Director with the approval of the Center Safety Committee, and shall report to the Reactor Supervisor.

f) The University Radiation Safety Officer (URSO), or his or her deputy, shall (in addition to other duties defined by the Director of Environmental Health and Safety) be responsible for overseeing the safety of Ward Center operations from the standpoint of radiation protection. He or she shall be appointed by the Director of Environmental Health and Safety with the approval of the University Radiation Safety Committee. He or she shall report to the Director of Environmental Health and Safety, whose organization is independent of the Ward Center organization, as shown on Chart I.

g) The Director of Ward Center, with the approval of the Ward Center Safety Committee, may designate an appropriately qualified member of the Center organization as Ward Center Radiation Safety Officer (WCRSO) with duties including those of an intra-Center Radiation Safety Officer; The University Radiation Safety Officer may at his or her 11

I discretion, and - M the concurrence of the Center Director, authorire the WCRSO to

.- perform some of tue specific duties of the URSO at Ward Center.

62 Review and Audit a) There will be a Ward Center Safety Committee which shall review the ZPR reactor status .

during the possession only phase, and through the decommissioning process, to assure that the reactor facility is used in a manner within the terms of the facility license and consistent with the safety of the public and of persons within the Laboratory.

b) The responsibilities of the Committee include, but are not limited to, the following;

1. Review and approval of rules, procedures, and proposed Technical Specifications;

2. Review and approval of all proposed changes in the facility that could have a significant effect on safety and of all proposed changes in rules, procedures, and Technical Specifications, in accordance with procedures in Section 6.3;

3. Determination of whether a proposed change, test, or experiment would constitute an unreviewed safety question or change in the Technical Specifications (Ref.10 CFR 50.59);

4. Review of the operation and operations records of the facility;

5. Review of unusual or abnormal occurrences and incidents which are reportable under 10 CFR 20 and 10 CFR 50;

6. Inspection of the facility, review of safety measures, and audit of operations at a frequency not less than once a year; and

7. Approval of appointments of Responsible Persons.

c) The Committee shall be composed of:

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1. one or more persons proficient in reactor and nuclear physics,

2. one or more persons proficient in chemistry or chemical engineering,

3. one person proficient in biological effects of radiation,

4. the Center Director, ex officio,

5. the University Radiation Safety Officer or his/her deputy, ex officio, and,

6. a member of the Executive Committee of the Ward Center Advisory Board or his/her deputy, ex officio, and,

7. the Reactor Supervisor, ex officio.

Fhe same individual may serve under more than one category above, but the minimum membership shall be seven. At least four members shall be faculty members.

d) The Committee shall have a written statement defining its authority and responsibilities, l the subjects within its purview, and other such administrative provisions as are required  ;

for its effective functioning. Minutes of all meetings and records of all formal actions of the i Committee shall be kept.

e) The chairman of the Committee sh4 Se elected by the Committee from its nembers, except l that the Center Director or Reactor Supervisor shall not serve as chairman. A quorum shall i consist of not less than a majority of the full Committee and shall include the chairman or l his or her designee. I f) The Committee shall meet a minimum of three times a year.

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1 63 Procedures a) Determination as to whether a proposed activity in categories 1 and 2 in Section 6.2b above l does or does not have a significant safety effect and therefor does or does not require

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approved written procedures shall require the concurrence of: l

1. the Center Director, and )

2. at least one other member of the Center Safety Committee, to be se!ected for relevant i expertise by the Center Director. If the Director and the Committee member disagree, or if in their judgment the case warrants it, the proposal shall be submitted to the full i Committee, and j

3. the University Radiation Safety Officer, or his or her deputy, who may withhold agreement until approval by the University Radiation Safety Committee is obtained.

Determinations that written procedures are not required shall be subsequently reviewed by the Center Safety Committee. The time at which detenninations are made, and the review and approval of written procedures, if required, are carried out, shall be a reasonable interval before the proposed activity is to be undertaken.

b) Determination that a proposed change in the facility does or does not have a significant safety effect and therefor does or does not require review and approval by the full Center Safety Committee shall be made in the same manner as for proposed activities under (a) above.

6.4 Emergency Plan and Procedures An emergency plan shall be established and followed in accordance with NRC regulations.

'Ihe plan shall be reviewed and approved by the Center Safety Committee prior to its submission to the NRC. In addition, emergency procedures that have been reviewed and approved by the Center Safety Committee shall be established to cover all foreseeable i emergency conditions potentially hazardous to persons within the Laboratory or to the public, including, but not limited to, those involving an uncontrolled reactor excursion or an uncontrolled release of radioactivity.

l 6.5 Physical Security Plan A physical security plan for protection of the reactor plant shall be established and l followed in accordance with NRC regulations.

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6.6 Action To Pc Taken In The Event Of A Reportable Occurrence l

In the event of a reportable occurrence, as defined in Section 1.1 of the specifications, the following actions shall be taken:

a) A report shall be made to include an analysis of the cause of the occurrence, efficacy of corrective action, and recommendations for measures to prevent or reduce the probability of recurrence. This report shall be submitted to the Center Safety Committee for review. I b) A report shall be submitted to the NRC in accordance with Section 6.8 of these specifications.

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6.7 Plant Operating Records a ) In addition to'the requirements of applicable regulations, in 10 CFR 20 and 50, records and logs shall be prepared and retained for a period of at least 5 years for the following items as a minimum: -

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1. normal plant operation, including power levels, a

2. principal maintenance activities; I

3. reportable occurrences;

4. equipment and component surveillance activities;

5. experiments performed with the reactor; ]

6. all emergency reactor scrams, including reasons for emergency shuts .vns. l I

b) The following records shall be maintained for the life of the facility: {

1. gaseous and liquid radioactive effluents released to the environs; 2.

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offsite environmental monitoring surveys; q

3. fuel inventories and transfers; i

4. facility radiation and contamination surveys; )

5. radiation exposures for all personne!; j

6. updated, corrected, and as-built drawir'gs of the facility. I 6.8 Benorting Requirements All written reports shall be sent within the prescribed interval to the United States i Nuclear Regulatory Commission, Washington, D.C. 20555, Attn: Document Control Desk, with l a copy to the Regional Administrator, Region 1. l In addition to the requirements of applicable regulations, and in no way substituting l therefor, reports shall be made to the U.S. Nuclear Regulatory Commission (NRC) as follows:

a) A report within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and telegraph to 'the NRC Operation Center and i

. Region I, of

1. any accidental release of radioactivity above permissible limits in unrestricted areas, whether or not the release resulted in property damage, personal injury, or exposure;

2. any reportable occurrences as defined in Section 1.1 of these specifications.

b) A report within 10 days in writing to the NRC Operation Center and Region I;

1. any accidental release of radioactivity above permissible limits in unrestricted area ,

whether or not the release rese t-xl in property damage, personal injury or em wure; the written report (and, to the exteat possible, the preliminary telephone e.nd 'h report) shall describe, analyze, and evaluate safety implications, and out. .

corrective measures taken or planned to prevent recurrence of the event;

2. any report-ble occurrence as defined in Section 1.1 of these specifications.

c) A routine report in writing to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555 and Region I, within 60 days after completion of the first 14

t calendar year of operating and at intervals not to exceed 12 months, thereafter, providing the following information:

1. a brief narrative summary of (1) changes in facility design related to reactor safety occurring during the reporting period, and (2) results of surveillance tests and ,

inspections; .

2. a summary of each change to the facility or procedures, tests, and experiments carried out under the conditions of Section 50.59 of 10 CFR Part 50;

3. a summary of the nature and amount of radioactive effluents released or discharged to the environs beyond the effective control of the licensee as measured at or prior to the point of such release or discharge;

4. a description of any environmental surveys performed outside the facility;

5. a summary of radiation exposures received by facility personnel and visitors, including the dates and time of significant exposure, and a brief summary of the results of radiation and contamination surveys performed within the facility.

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