ML20053A740
| ML20053A740 | |
| Person / Time | |
|---|---|
| Site: | Purdue University |
| Issue date: | 05/24/1982 |
| From: | PURDUE UNIV., WEST LAFAYETTE, IN |
| To: | |
| Shared Package | |
| ML20042C688 | List: |
| References | |
| NUDOCS 8205270228 | |
| Download: ML20053A740 (12) | |
Text
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Proposed Changes to APPENDIX A FACILITY LICENSE N0. R-87 TECHNICAL SPECIFICATIONS FOR THE PURDUE UNIVERSITY REACTOR DOCKET NO. 50-182 Change #1 - page 11, last line This proposal would change from 600 milliseconds to 1 second the time from the initiation of a scram condition in the scram circuit until the shim-safety rod reaches the rod lower limit switch.
The Hazards Summary Report specified the fast scram time to be approximately 500 milliseconds.
This time was,not sufficient due to the time needed by the dash pot, which limits the rod impact at the lower end of the rod travel.
Therefore, the scram time in the Technical Specifications, approved November 28, 1978, was specified "not to exceed 600 milliseconds".
Methods developed to measure this value actually measured the rod release and insertion time, not the scram time.
This method measured the value for the
" fast" scram circuits that anticipate a scram condition and reduce the magnet currents until the magnets can no longer support the rods and they drop at the trip point. A new measurement procedure indicates that this value is too low for the " slow" scram circuits which interrupt the power to the regulated power supplies for the control rod magnets.
This requires an average of 60 milliseconds additional time to drain off the stored energy in the power supplies until the rods drop, thus causing the measured slow scram time to exceed 600 milliseconds.
Assume a ramp increase in reactivity is produced by withdrawing all control rods simultaneously with the failures of the period interlock, the 820527017S
setback trips, the period scrams, and the control rod interlocks that prevent withdrawal of all control rods simultaneously.
Further assume a maximum allowable excess reactivity of 0.006 [ in the reactor and a reactor period of three seconds at the time the limiting safety setting of 1.20 kw is reached.
If the high level fast scram is lnoperable the slow scram would allow the power level to increase for an additional 60 milliseconds before the shim-safety rods would drop, and the trip point would only be increased from 1.20 kw to 1.22 kw.
Even if the reactor should be placed on a one second period, which corresponds to a reactivity increase of 0.006 f, the maximum power would only be 1.27 kw, well below the Safety Limit of 50 kw.
Therefore, no additional hazard is considered to exist.
Change #2 - page 12, footnote designation for Table II This change from (a) to (c) is proposed to avoid confusion with the footnotes in Table I.
Change #3 - page 25, line 6 Change the name Department of Nuclear Engineering to School of Nuclear l
Engineering.
This change occurred while the technical specifications were I
being written, but this reference did not get corrected.
Change #4 - page 31, part 6.2.3 It is proposed to change this section to read, "The COR0 or a subcommittee thereof shall meet quarterly, at intervals not to exceed 16 weeks.
The COR0 shall meet semiannually at intervals not to exceed 7 months". This change would clarify the original intent of the specification.
Change #5 - page 32, part a, last phrase at bottom of the page By changing "at least once per 12 months" to "to be done annually at intervals not to exceed 14 months" would clarify the original intent of the specification.
Change #6 - page 33, part b Change " entire facility staff" to " licensed facility staff" because it is the licensed facility staff that participates in the requalification program and not the entire facility staff. Also change the last phrase to "to be done annually at intervals not to exceed 14 months".
These changes would clarify the original intent.
Change #7 - page 33, part c Change "at least once per 6 to 12 months" to "to be done annually at intervals not to exceed 14 months".
This will further clarify the original intent of the specification.
Change #8 - page 33, part d Change "at least once per 24 months" to "to be done biennially at intervals l'
not to exceed 28 months".
This will clarify the intent of the specification.
Change #9 - page 33, part e Change "at least once per 24 months" to "to be done biennially at intervals not to exceed 28 months".
This will clarify the original intent of the specification.
Change #10 - page 35, line 7 The word " Operations" should be changed to "Nonroutine operations" to better clarify the original intent of this specification.
The last two I
paragraphs of Section 6.4 should be moved to the left to eliminate l
any confusion that they are part of Subsection 6.4.7 They.are descriptive l
l of how the procedures should be used, not part of the list of procedures.
Change #11 - page 38, line 8 Change " abnormal" to " reportable" to bring this sentence to agree with the original intent of the rest of this paragraph.
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__m 11, consequences than the maximum credible accident analyzed in the llazard Summary Report.
Specification 3.1.g along with 3.1.a assures that the reactor is capable of being shut down in the event of a positive reactivity insertion caused by the flooding of an experiment.
3.2 Reactor Safety System Applicability This specification applies to the reactor safety system and other safety-related instrumentation.
Objective The objective is to specify the lowest acceptable level of performance or the minimum number of acceptable components for the reactor safety 1
i i
system and other safety related instrumentation.
Specification The reactor shall not be made critical unless the following condi-1 f
tions are met:
l The reactor safety channels and safety-related instrumentation are a.
operable in accordance with Tables I and II including the minimum number of channels and the indicated maximum or minimum set points.
b.
Both shim-safety rods and the regulating rod shall be operable.
c.
The time from the initiation of a scram condition in the scram circuit until the shim-safety rod reaches the rod lower limit switch shall not exceed one second.
12.
TAltLE 1.
SAFFTY CilANNEl.S RI'.QlflRED FOR OpERATLON
?tinimun channel Number Setpoint Function II3uired 1("
2 cps 2 cps rod withdrawal Log count rate and period interlock 12 sec. period Setback 7 sec. period Siw scram 1.og N and period I
12 sec. perital Setback 7 sec. pertoil Slow scram 7 sec. perioil Fast scram 12W. power Slw scram Linear 1
1IM. range Setback 1207. range Slow scram Safety 1(b) llM. pwer Setback 12 W. power Fast scram blanual Scram (console) 1 Slow scram (hallway) 1 Slow. scram (a)Not required af ter leg N-period channel comes on scale.
(b) Required to be operable but not on scale at startup.
Tall!I li. SAFETY-RELATED CllANNELS (AREA RADI ATION F10NITORS)
!!ininum Channel Number Setpoint Function Required (c) g I
pool top iaonitor 1
50 mR/hr or Slow scram 2x full pwer j
background Water process I
75 mR/hr Slow scram console monitor 1
75 mR/hr Slow scram l
Continuous air 1
Air sampling sampler
(") For periods of time, not to exceed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of operation, aradiationl monitor may be replaced by a gamma sensiLive lustrument which has its own alarm or is kept under periodic visual observation, i
i I
l
25.
5.0 DESIGN FEATURES 5.1 Site Description 5.1.1 The reactor is located on the ground floor of the Duncan Annex of the Electrical Engineering Building, Purdue University, West Lafayette, Indiana.
5.1.2 The School of Nuclear Engineering controls approximately 5000 square feet.
5.1.3 Access to this area is restricted except when classes are held here.
5.1.4 The reactor room remains locked at all times except for the entry I
or exit of authorized personnel.
5.1.5 The PUR-1 is housed in a closed room designed to restrict leakage.
5.1.6 The minimum free volume of the reactor room shall be 15,000 cubic feet.
5.1.7 The ventilation system is designed to exhaust air or other gases from the reactor room through an exhaust vent at a minimum of 50 feet above the ground.
5.1.8 Openings into the reactor room consist of the following:
l a.
Three personnel doors i
b.
Two locked transformer vault doors c.
Air intake d.
Air exhaust e.
Sewer vent I
5.2 Fuel Assemblies 5.2.1 The fuel assemblies shall be MTR type consisting of aiutainum clad plates enriched to approximately 93% in the U-235 isotope.
5.2.2 A standard fuel assembly shall consist of 10 fuel plates containing a maximum of 165 grams of U-235.
5.2.3 A control fuel assem' '- shall consist of 6 fuel plates containing a maximum of 99 r of U-235.
31.
6.2 Review and Audit 6.2.1 A Committee on Reactor Operations (CORO) shall report to the Radiological Cont rol Committee on matters of Radiation Safety and the llead, School of Nuclear l'ngineering on matters of administration and safety.
CORO will advise the Reactor Supervisor on those areas of responsibility specified in Sections 6.2.5 and 6.2.6.
The mininum qualifications for persons on the CORO shall be five years of professional work experience in the discipline or specific field he represents. A baccalaureate degree may fulfill four years of experience.
6.2.2 The CORO shall have at least 7 (seven) members of whom no more than a minority shall be directly concerned with the administration or direct use of the reactor.
These members shall include the following:
a.
The Chairman, a responsible, senior technical person, knowledge-able in the field of reactor technology, who does not have line responsibility for day-to-day operation of the reactor.
b.
A senior radiols zical control officer.
c.
The Purdue University Superintendent of Safety and Security.
d.
The Reactor Supervisor.
e.
Three senior selentific staff members.
6.2.3 The CORO or a subcommittee thereof shall meet quarterly at intervals not to exceed 16 weeks. The CORO shall meet semiannually at intervals not to exceed 7 months.
6.2.4 A quorum shall consist of not less than a majority of the full l
Committee and shall include the chairman or his designated alternate.
l 6.2.5 The CORO shall review:
a.
Safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments, conducted without NRC l
approval und the provision of Sect ion 50.59, 10 CFR, to
32.
verify that such actions did not constitute an unreviewed safety question.
b.
Proposed changes to procedures, equipment or systems that change the original intent or use, and are non-conservative, or those that involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
c.
Proposed tests or experiments which are significantly different f rom previous approved tests or experiments, or those that involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
d.
Proposed changes in Technical Specifications or license.
e.
Violations of applicable statutes, codes, regulations, orders, Technical Specification, license requirements, or of internal procedures or instructions having nuclear safety significance.
f.
Significant operating abnormalitic's or deviations from normal and expected performance of facility equipment that affect nuclear safety, g.
Events which have been reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC in t
writing.
h.
Audit reports.
6.2.6 AUDITS l
l Audits of f acility activities shall be performed under the l
)
cognizance of the CORO but in no case by the personnel responsible for the item audited.
Individual audits may be performed by one individual who need not be an identified CORO member. These audits shall examine the operating records and encompass:
a.
The conformance of facility operation to the Technical Specifications l
and applicable license conditions, to be done annually at intervals not to exceed 14 months, i
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s 33.
b.
The performance training and qualifications of the lice.nsed facility staff, to be done annually at Intervals not to exceed 14 months.
c.
The results of all actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety, to be done annually at intecvals not to exceed 14 months.
d.
The Facility Emergency Plan and impicmenting procedures, to be done biennially at intervals not to exceed 28 months.
The Facility Security Plan and implementing procedures, to be c.
done biennially at intervals not to exceed 28 months.
f.
Any other area of facility operation considered appropriate by the CORO or the Reactor Supervisor.
6.2.7 RECORDS Records of CORO activities shall be prepared and distributed as l
indicated below.
l
[
a.
Minutes of each CORO meeting shall be prepared and forwarded to the Reactor Supervisor within 30 days following each meeting.
b.
Reports of reviews encompassed by Section 6.2.5 e, f, and-g above, shall be prepared and forwarded to the Reactor Supervisor within 30 days following completion of the review.
c.
Audit reports encompassed by Section 6.2.6 above, shall be forwarded to the CORO Chairman and to the management responsible for the areas audited within 30 days after completion i
r of the audit.
l L
l
35.
6.4.4 Emergency conditions involving potential er actual release of radio-activity, including provisions for evacuation, re-entry, recovery, and medical support.
6.4.5 Maintenance procedures which could have an effect on reactor safety.
6.4.6 Experiment installation, operation, and renoval.
6.4.7 Implementation of the Security Plan and Emergency Plan.
Non-routine operations which require the sequential performance of a series of sub-tasks shall be carried out with the written procedure at the console.
To assure adherence to the documentation of the procedure, each step will be entered in the log book as it is completed.
Substantive changes to the above procedures shall be made only with the approval of the CORO.
The Reactor Supervisor may make changes to pre :edures which do not change the intent of the original procedure.
All such changes to the procedures shall be documented and subsequently reviewed by CORO.
6.5 Operating Records 6.5.1 The following records and logs shall be prepared and retained for at least five years:
a.
Normal f acility operc t ion and ma intenance.
h.
Reportable occurrences.
c.
Tests, checks, and measurements documenting compliance with surveillance requirements.
d.
Records of experiments perforned.
Records of radioactive shipments.
e.
f.
Changes of operating procedures.
g.
Facility radiation and contamination surveys.
I
38 6.6.2 Non-Routine Reports a.
Reportable Occurrence Reports In the event of a reportable occurrence (defined in 1.0) notification shall be made 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 Director of the Regional Regulatory Operations Office (copy to the Director of Licensing), followed by a written report within 10 days to the Director of the Regional Regulatory Operations Office.
The written report on these reportable occurrences, and to the extent possible the preliminary telephone and telegraph notification shal1:
(a) descrlhe, analyze, and evaluate safety implications, (b) outline the measures taken to assure that the cause of the condition is determined, (c) indicate the correct ive act ion (including any change >. made to the procedures and to the quality assurance program) taken to prevent repetition of the occurrence and of similar occurrences involving similar components or systems, and (d) evaluate the safety implications of the incident in light of the cumulative experience obtained from the record of previous failures and nalfunctions of similar systems and components.
- Telegraph notification may he sent on the next work ing day in the event of a reportable occurrence during a weekend or holiday period