ML20206G581

Amend 6 to License R-89,modifying Some ACs in Section 6 of TSs in Response to 990308 Ltr

ML20206G581
Person / Time
Site:	05000097
Issue date:	04/28/1999
From:	Michaels T NRC (Affiliation Not Assigned)
To:
Shared Package
ML20206G566	List: ML20206G563 ML20206G581 ML20206G584
References
R-89-A-006, R-89-A-6, NUDOCS 9905100066
Download: ML20206G581 (9)

Text

4 pa n o g i UNITED STATES g

j t

NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20666-0001 l

s r

CORNELL UNIVERSITY ZERO POWER REACTOR DOCKET NO. 50-97 AMENDMENT TO FACILITY LICENSE I Amendment No. 6 Licensee No. R-89

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A. The application filed by Cornell University (the licensee), dated March 8,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the regulations of the Commission as stated in 10 CFR Chapter I; B. The facility will be maintained in conformity with the application, the provisions I of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the  !

public and (ii) that such activities will be conducted in compliance with the rules and regulations of the Commission: l D. The issuance of this amendment will not be inimical to the common defense 3 and security or to the health and safety of the public; E. This amendment is issued in accordance with 10 CFR Part 51 of the regulations of the Commission and all applicable requirements have been satisfied; and )

l F. Prior notice of this amendment was not required by 10 CFR 2.105 and '

publication of notice for this amendment is not required by 10 CFR 2.106.

l l

i I

)

l 5100066 990428 .

p ADOCK 05000097 PDR l

2

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license .anondment, and paragraph 2.C.2 of License No. R-89 is hereby amended to read as follows:

2. The Technical Specifications contained in Appendix A, as revised through Amendment No. 6 are hereby incorporated in the license. The licensee shall maintain the facility in accordance with the Technical Specifications as amended.

3. This license amendment is effective on the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION S.

Theodore S. Michaels, Senior Project Manager Events Assessment, Generic Communications and Non Power Reactors Branch Division of Regulatory Improvement Programs  ;

Office of Nuclear Reactor Regulation I

Enclosure:

Appendix A Technical Specifications Date of Issuance: April 28, 1999 I

1 l

l l

l

f

• ENCLOSURE TO LICENSE AMENDMENT NO. 6 FACILITY LICENSE NO. R-89 DOCKET NO. 50-97 Replace the following pages of the Appendix A Technical Specification with the enclosed.

pages. The revised pages are identified by Amendment number and contains verticallines indicating the areas of changes.

Remove insert 5 5 6 6 7 7 8 8 9 9 10 10 11 1

1 1

1 l

m. .

6. Administrative Controls 6.1 Organization and Responsibilities of Personnel a) The Zero Power Reactor, located in the J. Carlton Ward, Jr. Laboratory of Nuclear Engineering, shall be 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 I 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 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 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 ot the position. He or she shall report to the Vice Provost. l 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 discipline, 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 l 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 s.tuations to the Reactor Supervisor and/or Center Director. Responsible Persons shall possesa a Senior Operator's license, shall be appointed by the Center Director with the approval of the I Center Safety Committee, and shall report to the Reactor Supervisor.

f) The University Radiation Safety Officer (URSO), or his or her deputy, shall (,n addition ,

to other duties defined by the Director of Environmental Health and Safety) be responsible l 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 3 Center Radiation Safety Officer (WCRSO) with duties including those of an intra-Center i 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.

ZPR Tech. Specs. @6 - Amendment #6 5

9 5

. l d

r r te oa nB e

Cy r n

_ib do r s l

i" o sR r

ai r eP r o v s Wd e oi s Pe Z A c ,

n t c vr l bt y

i e

c 1 a epe 1 ius S Ru nD o n r S p -

t s a e sO o e h rc l

R t

s v c ou o o r r t 1 v 1 r Pf es o a cN e

o r r r e e i o P Dfr i

V c R e

- t r -

n e -

e c C i f

f

- e dr 4 r eOy rt t e a t nt ei nm t W ee Cfa hy r

e: d n

em .

dS t t a e r

Co oiir s l

r u dC l

a no rbo oit l e

c t

c r

ayt Wia t fs sc na er ul l

s u r

ys t e

- Wf e a

i d

a eoeCoa n pR a S i r S t

i se rt e s S R . i l

sR eAmete s

va l

a n

v ur t n -

• u ofI GatmiM o e goRGa c i

i - t nT d - ~

o a z

Ufo 1 i s

l

- osT a i i l e r -

d l a e d a

n l i nr a en na P -

- Aa R g r

r ~

oo - O CB -

~

~

1

- y y -

- t tr e t e a -

- yaf yf e t ae

- h t

iSs d iSt s i t

C rdr r r.? en va Bo a 1 e v im nm o 1 'j i i t

nh t nao _

Ul a UiC d

c a I

I R ~

~

OJ i

l i

b i

t s ht f s  :

y n u f a n t e p l a .* t o i d t e d S p l i

s n m I neS s i

b e ea I y r ar y e i P

r dCs e i

rl t oae ey*R gr f t

e R s n

sdc e

t t f cna ao a t n o 1 e 1 r niv 1 eeS l1 nt s 1 S p c Pa se r r a r e s af i

V e eS imd Dnn Mo f

n o i y

t m t R e -

r ci oa b f' f i

t r n y o i t o

La

• y, i

Vl i i

r a o c i

n i v i d ht p i e c n u p l

a a o S F E R  :

dA A P nf e o f of o ge e e en n n i i i LL L L m s3 g no ,* m e tag

6.2 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:

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. l 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 responsibilities, 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 Committee shall be kept.

c) The chairman of the Committee shall be elected by the Committee from its members, except l that the Center Director or Reactor Supervisor shall not serve as chairman. A quorum shall consist of not less than a majority of the full Committee and shall include the chairman or his o. her designee.

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

ZPR Tech. Specs. 56 - Amendment #6 7

63 Procedures a) Determination as to whether a proposed activity in categories 1 and 2 in Section 6.2b above does or does not have a significant safety effect and therefor does or does not require approved written procedures shall require the concurrence of:

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 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.

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 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 release of radioactivity.

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

6.6 Action To Be Taken In The Event Of A Reportable Occurrence 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.

b) A report shall be submitted to the NRC in accordance with Section 6.8 of these specifications.

ZPR Tech. Specs. 56 - Amendment #6 j 8

6.7 Plant Oceratine 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:

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.

b) 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 contamination surveys;

5. radiation exposures for all personnel;

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

6.8 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 Administrator, Region I.

In addition to the requirements of applicable regulations, and in no way substituting 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 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 areas, 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 i report) shall describe, analyze, and evaluate safety implications, and outline the {

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

2. any reportable occurrence as defined in Section 1.1 of these specifications, j t'

c) A routine report in writing to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555 and Region 1, 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:

ZPR Tech. Specs. 96 - . Amendment #6 9

3

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 rad!oactive 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.

l 1

i ZPR Tech. Specs. s6 - Amendment #6 10