ML20198F179
| ML20198F179 | |
| Person / Time | |
|---|---|
| Site: | Rhode Island Atomic Energy Commission |
| Issue date: | 07/31/1997 |
| From: | Tehan T RHODE ISLAND, STATE OF |
| To: | Mendonca M NRC (Affiliation Not Assigned) |
| Shared Package | |
| ML20198F184 | List: |
| References | |
| NUDOCS 9708110207 | |
| Download: ML20198F179 (7) | |
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TATE OF ltilODE lAAND AND PitOVIDENCE PLANTATIONS 1(llODE ISI.AND ATOMIC ENEl(GY COMhflSSION Nuclear Scieme Center South Ferry }(oad Narragansen, ILI. 02M21197
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July 31, 1997 i
Docket 11o. 50-193 Mr. Marvin Mendonca, Senior Project Manager
!Jon-Power Reactors, Decommissioning and Environmental Project Directorate Division of Reactor Projects - III/IV/V U.S. !Juclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Mendonca:
This letter concerna a request for an amendment of the RIAEC license by changes to the Technical Specifications. Upon completion of a thorough review of the Technical Specifications, the RIllSC staff requests the following changes.
1.
page 7 Section 1.25.5
& 6 Reportable Occurrence FROM:
5.
An uncontrolled or unplanned release of radioactive material from the restricted area of the facility 6.
An uncontrolled or unplanned release of radioactive material which results in concentrations of radioactive materials within the restricted area in excess of the limits specified in Appendix B, Table 1 of 10CFR20:
TO:
1 An uncontrolled or unplanned release of radioactive material which ressults in concentrations of radioactive materials inside or outside the restricted area in excess of the limits specified in lionendix B. of 10CFR2Qt 1
Deleted.
Basis for Change:
Combine paragraphs 1.25.5 and 1.25.6 which ' incorporates limits on releases of radioactive material from a restricted area.
2 '.
page 14 Section 2.2.1 Limiting Safety System Settings in the Forced Convection Mode FROM:
Objective j
s This specification applies to the setpoint for the safety channels monitoring reactor power, primary coolant flow, pool level and core inlet and outlet temperatures to assure 9708110207 970731 POR ADOCK 05000193 el(({\\.\\{
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a that the maximum fuel temperature permitted is such that no damage to the fuel cladding will result in the forced convection inode.
To:
Objectives This specification applies to the setpoint for the safety channels monitoring reactor power, primary coolant flow, pool level and care outiot temocrature to assure that the maximum fuel temperature permitted is such that no damage to the fuel cladding will resalt in the forced convection mode, i
l Basis for change:
Core inlet temperature (Tu was removed during Admendment 23, this l
should have been removed also.
3.
page 16 Section 2.2.2.1 Limiting -Safety System settings in the Natural Convection - Mode FROM:
Paramoter LSSS H
(min).
23.7 ft. above the top of the active core Toi.
Parameter Lsas H
(min) 23.7 ft.
l Basis for Change:
Text 'above the tcp of the active core" is contained in previous paragraph. Text is ommitted for consistency.
4.
page 20 Section 3.2 Reactor safety system Delete second paragraph of objective.
Basis for Change: Typo, Paragraph repeated.
5.-
page 25 Section 3.3(a) Primary Coolant Water FROM:
3.
The concentration of radioactive materials in the primary coolant is maintained at a level such that the reading on the reactor bridge radiation monitor does not exceed 10 mram/hr.
TO:
3.
The primary coolant shall be analyzed for radioactivity.
= Basis for Change:
This statement is misleading. The concentration of radioactive materials in-the primary coolant is not " maintained...", Instead, the measurements are used to assist evaluation of the overall conditions of the, reactor pool water.
The dose and alarm set point of the reactor bridge radiation monitor are discussed in Table 3.2 and should not be part of this specification.
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- 6..page 29 section 3.7.1.2 Radiation Monitoring Systems l
FROM:
2.
When the reactor is operating, at least one constant air monitoring unit (Table 3.2.10) located in the confinement building shall be-operating.
Temporary shutdown of this unit shall be limited as in 3.7.1 I
above.
To:
2.
When the reactor is operating, at least one-constant air monitoring unit (Table 3.2.11) located in the i
+
confinement building shall be operating.
Temporary shutdown of this unit shall be limited as in 3.7.1 above.
Basis for change:
Correct reference to appropriate section of Table j
3.2.
4 7.
page 29 section 3.7.1.3 Radiation Monitoring Systems FROM:
3.
The reactor shall not be continuously
- operated j'
without a minimum of one area radiation monitor (Table 3.2.7) on the ' ground floor level' of the reactor building and one area monitor (Table 3.2.5) 1 over the reactor pool (reactor bridge) operating and-capable of warning personnel of high radiation 1
levels.
i TO:
3.
The reactor shall not be continuously
- operated without a minimum of one area radiation monitor i
(Table ' 3. 2. 8 ) on the ' ground floor-level' of the reactor building and one area monitor (Table 3.2.6)-
over the reactor pool (reactor bridge) operating and capable of warning persor.nel cf high radiation levels.
Basis for change:
Correct reference to appropriate section of Table 3.2.
8.
page 31 section 3.7.2.a Airborne Efflupats FROM:' Basest The limits established in specification 3.7.2 incorporate a dilution factor of 105'for offluents released through the
-exhaust stacks.
This dilution factor is more conservative i
than thatEcalculated f roni actual meteorological data which represents the; lowest dispersion factor determined-and the
-highest frequency of wind in any sector.
Because of the:use of the most conservative measured values of wind directional frequency and dispersion factors, this dilution factor will l
assure that concentrations : of radioactive material in 3
unrestricted areas around-the Rhode Island Nuclear Science t'
Center-will be far below the limits of 10CFR20.
(Refer to letter dated April-16, 1963 sent to the NRC in connection with license. questions.)
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This dilution-fcctor is used for calculating maximum ground concentration down wind for noble gases.:The_SAR contains calculations for doses from the iodine at the 48 meter distance.
TO:
Bases:
The limits estab13shed in specification 3.7.2 incorporate a dilution ' f actor of 4x104 for offluent concentrations l-released through the exhaust stacks.
I l
This dilution factor is cased on a dispersion factor (%/O =
10-5 3 cfg3) calculated from actual' meteorological data which is determined using the highest frequency of wind in any sector.
r Because of the use of the most conservative measured values il of wind directional frequency and dispersion factors, this dilution factor will assure that concentrations of radioactive material in unrestricted areas around the Rhode Island Nuclear Science Center will be far below the limits of 10CFR20.
' (Refer to lett <:.r dated Apri1~ 16, 1963 sent to the NRC in connection with license questions.)
This dilution fastor is used for calculating maximum ground-concentration c,i
.oble gases down' wind vs. exhaust stack effluen*. concentrations.
The-SAR contains calculations for doses from the iodine'at L
the 48 met'r distance.
Basis for change:
To make clear a distinction between the dilution factor used for the effluent concentration calculation and the-dispersion factor used for an effluent release rate calculation developed frora X/O data.
.9, page 31-Section 3.7.2.a Effluents FROMt.
-a.
Liquid Effluents To:
b.
Liquid Effluents l
Basis-for change: Typo correction.
- 10. page 34 section 3.8 Limitations. on Experiments FROM:
Bases:
Specifications 1 through 5,
8. and 9 are intencad to reduce the likelihood of damage to reactor components and/vr radioactivity 4
~
releases resulting from experiment failure and, along with the reactivity restriction of pertinent specification in 3.1, serve as a guide for the rev_ew and approval of new and untried experiments i
by the operations staff as well as the Reactor Utilizat!3n Subcommittee.
TO:
Bases:
Specifications 1 through 5,
8 and 9 are intended to reduce the
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likelihood of damage to reactor components and/or radioactivity releases resulting from experiment failure and, along with the I_.
reactivity restriction of pertinent specification in 3.1, serve as a guide for the review and approval of new and untried experiments by the operations staff as well as the Nuclear and Radiation Safetv
. Subcommittee.
Basis for change:
Name change originally approved in Amendment # 21, v:
l 11.
page 44 Section 4.4,4.5,4.6.f RINSC Confinement and Emergency Exhaust System 1
FROM:
f.
the exhaust rate through the cleanup system shall
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not exceed 4500 CFM with not more than 1500 CFM coming from the reactor building and passing through the scrubber filtr.r The remaining air will be provided by a separate blower from an uncontaminated source.
TO:
f.
the exhaust rate through the emergency cleanup system shall not be more than 1500 CFM coming from the reactor building and passing through the scrubber filters. Dilution air will be provided by a separate blower from an uncontaminated source.
Basis for change:
Referring to the drawing below, the air cleanup system is defined an the charcoal and absolute filters and cleanup blower A maximum flow rate limit through the charcoal bed is required to provide for an acceptable atmospheric residence time in the charcoal (ref. Reg.
Guide 1.52).
The dilution air blower, which is not part of the cleanup system, maximum flowrate limit from the original specifications (4500 CFM minus the emerg. cleanup flow rate) has been removed to allow for as much dilution air as possible.
5 1
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EXHAUST Containment Building d
i Cleanup Blower r
3 Absolute &
A i
- Charcoal Filters
)
(
-J max 1500 cfm Uncontaminated Air / Dilution Supply i
max 0000 dm Lab Hood Blower 12.
page 48 section 4.9.c Reactor Core Components FROM:
c.
LEU Fuel Elements TO:
b.
LEU Fuel Elements
'l Basis for change: Typo correction.
13. - page 59 section 6.4.d Review at.d Audit FROM:
d.
Determination of whether a proposed change, test, or expet'iment would constitute an unreviewed safety
- question which may require a change to the Technical Specifications or facility license.
.TO:
d.
' Determination of whether a proposed change, test, or e:cperiment would constituce - an unreviewed safety question or which may require a change to the "echnical Specifications or facility license.
Basis for change: Typo correction.
6 J
t e
14. - page 62 section 6.8. Reporting Requirements FROM:
1.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, a report by telephone through the NRC Operation Center,-301-951-0550 and the NRC Region 1:
TO -
1.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, a report by telephone through the NRC Operations Center, Washington, DC and the NRC Region 1:
Basis for Change Remove telephone listing from tech specs. An updated telephone
^
' call list is maintained at the RINSC.
l :-
- 15. page 63 section 6.8.1.c Reporting Requirements l
FROM:
1.c. Any reportable occurrences as defined in paragraph 1.35 of these specifications.
TO:
1.c. Any reportable occurrences as defined in paragraph 1.25 of these specifications.
Basis for change's Reference correction.
- 16. page. 63 section 6.8.2 Reporting Requirements FROM:
2.
A written report within 14 days in the event. of a reportable occurrence, as defined in Section 1.35, a through e.
The report shall:
To:
- 2. 4'he written report shall be sent within 14 days. The-report shall:
Basis for change:
Remove unnecessary definition reference.
Enclosed are the new Technical Specifications pages. If there are e.ny questions regarding these changes, you can reach me at (401) 789-9391.
Sincere fb
.:. Terry 'ehan Direr or cc om Dragoun, U.S. NRC, Region ;
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