ML20135E353
ML20135E353 | |
Person / Time | |
---|---|
Site: | Rhode Island Atomic Energy Commission |
Issue date: | 12/05/1996 |
From: | Tehan T RHODE ISLAND, STATE OF |
To: | Mendonca M NRC (Affiliation Not Assigned) |
References | |
NUDOCS 9612110195 | |
Download: ML20135E353 (18) | |
Text
__
DEC-5-96 THU 14:47 R 1 NUCLEAR SCIENCE CTR M NO. 40 DB24201 W
TATE OF RHODE ISLAND AND PROVIDENCE PLANTATION RHODE ISLAND ATOMIC ENERGY COMMISSION Nuclear Science Center South Ferry Road Narragansett, R.I. 02882 1197 December 5, 1996 Docket No. 50-193 Mr. Marvin Mendonca, Senior Project Manager Non-Power Reactors, Environmental Project DirectorateDecommissioning and l
Division of Reactor Projects - III/IV/V U. S. Nuclear Regulatory Commission (NRC) l Washington, DC 20555 i
Dear Mr. Mendonca:
As discussed in our telephone conversation of December 4,
1996, this letter requests a one time extension of the i
annual Technical Specification (T,S) surveillance periodicity for safety blade testing (T.S. 4.1.1,4.2.8) and reactivity calculations (T.S.
4.2.6, 4.2.7), This testing is due in late December, (Surveillance Intervals).1996 under the 15 months limit of T.S 1.38 l
month extension be granted to allow this testing to be doneIt is reque l
in January, is enclosed to accomplish this rescheduling 1997. A revision The reactor was not calendar year because of operated for most of the 1996 work to add another loop and upgrade primary and secondaryex pumps. As a result, there is a large backlog of work to be completed that should be done by December 25. Additionally, requires reactor op supervisor has been hired and will report a new reactor of January at which time the tests will be done as soon asin the beginn possible.
It is important that the new staff member see rod l
testing and reactivity calculations in order to qualif i
Senior Reactor Operator.
y as Delaying these tests less than a month will provide vital training while eliminating the need to do another full set of rod testing early next ye ar, I
-o 0
i
- - - - - ~ ~,.
DEC-5-96 THU 14:48 R I NUCLEAR SCIENCE CTR FAX NO. 4017824201 P.03 Mr. Marvin Mendonca
. January 25, 1994 Page 2 The rod control system and the blades have been operating properly since return to operation in Septe b Safety blade drop times were conducted satisfactorily on m er.
October 21, 1996.
Safety blade satisfactorily on October 21, inspections were conducted reactivity data is submitted 1996. Previous blade worth and with the current performance o. This data corresponds well has been stable and estimates f the reactor at power which start up have agreed with previous data closelyof critical position during Committee on December 4,This request was reviewed by the React request this extension.
1996 and the decision was made to a
on Sincerely
&\\d Terr ehan Dir or TT:cd
Enclosures:
Revised T.S. Pages 37,39,40 Reactor Test Data Copy to:
T. Dragoon, Region One Reactor Utilization Committee 1
N o es e-y== ausy q g.e
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DEC-5-96 THU 14:48 R I NUCLEAR SCIENCE CTR FAX N0. 4017824201 P.04 TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50.!93.1.icense R.95 Revision i 4.0 SURVEILLANCE REQUIREMENTS Surveillance tests for Reactivity Limits (4.1), Reactor Safety System (4.2),
Surveillance of Experiments (4.8) and Reactor Components (4.9) may be - deferred for periods of reactor shutdown providing they are performed prior to restart 15.1 4.1).
Surveillance tests for the (ANS performed as :;tated in the appropriate sections:following will be Water Coolant Sytem (4.3)
Confinement and Emergency Exhaust System (4.4, 4.5, 4.6)
Radiation Monitoring System and Effluents (4.7) i 4.1 Reactivity Limits Applicability:
)
1 This specification applies to the surveillance requirements for reactivity limits.
Objective:
i To assure that the reactivity limits of Specification 3.1 are not exceeded.
Specification:
\\
iv y ths and insertion ra shall be eas e annually;"
a.
b.
whenever the core is changed from the startup core to the three other cores as analyzed and specified in the SAR (Part A.
Section V).
2.
Shim safety blades shall be visually inspected and checked for swelling at least annually.
- To BE CONDUCTED AT 16140 NTH INTERVAL IN JANUARY 1997 Page 37
.-,-n.
Amendment tio.18
_ _ ~
i DEC-5-96 THU 14:49 R 1 NUCl. EAR SCIENCE CTR FAX NO. 4017824201 P.05 TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50193. License R-95 Revision I a.
Prior to each reactor startup following
(
a period when the reactor was secured; b.
After a
channel has been repaired or deenergized.
1 2.
A channel calibration of the safety channels listed in Table 3.1, which can be calibrated, shall be performed annually.
l 3.
The radiation monitoring system required in Table 3.2 shall be operable prior to every reactor l
startup for which safety system channel tests are i
i i
required as in 4.2.1.
If the system has been repaired, the system shall be operable prior to use.
4 Shim safety blade release-drop time sha'll be measured annually.
1 5.
Shim safety rod release-drop time shall be l
measured whenever the shim safety rod's core location is changed or whenever maintenance is performed which could effect the rod's drop time.
i (Specification 3.2.3)
Shutdown Margin (Specification 3.1.1) 6.
The shutdown margin shall be determined annually.
The determination will be made in accordance with operating procedures.
7.
Excess Reactivity (Specification 3.1.2)
The excess reactivity shall be determined l
annually. ", It shall be determined when a new core is configured as described in the SAR (Part A,Section V).
The determination will be made in i
accordance with operating procedures.
j
- To BE CONDUCTED AT 16 MONTH INTERVAL IN JANUARY 1997
.~,,r,,,...
Amendment No, 18
DEC-5-96 THU 14:49 R 1 HUCLEAR SCIEHCE CTR FAX H0. 40 n824201 W
.~
TECHNICAL SPECIFICATIONS l
Rhode
!siand l
Nuclear Science Center Docket 50193.1.icense R.95 l
Revision I 8.
Reactivity Insertion Rate (Specification 3.2.4) i i
The reactivity insertion rate shall be measured I
annually.
- It shall be determined when a new core is configured as described in 1
The determination will be made in accordance with written procedures.
- TO BE CONDUCTED AT 16 MONTH INTERVAL IN JAN Bases:
Pr'estartup tests of the safety system channels operability.
assure their detected by normal intercomparison of chan i
is not channel operability check of the neutron The flux level channels assures that monitor the parameter they are measuring.the dete Radiation monitors are checked for proper operation in Specification 4.2.3.
Calibration and setpoint verification involve of a calibration source and significant personnel radiation use exposure.
monitors is adequateIt is determined that annual calibration of t
since they displayed excellent stability over many years of operation.
The measured release-drop times of the have been consistent over many years.
shim safety blades
{
parameters is considered adequate to detectAnnual check of these which could change the release-drop time.
any deterioration caused by rod misalignment, could Binding or rubbing result from maintenance:
therefore, release drop times will be checked after such maintenance.
4.3 Water Coolant System Primary Coolant System a.
Applicability:
This specification applies to the surveillance of the primary coolant system.
Page 40 Amendment No. 18
....,,.. ~... - -
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DEC-5-96 THU 14:49 R I NUCLEAR SCIENCE CTR FAX N0, 4017824201 P.07 Rhode Island Nuclear Science Center _...
....v cocnu Y COMMISSION i
Date:
10/4/95 l
To:
Reactor Staff From:
Wayne Simoneau Subj:
Annual Reactor Tests In accordance with Technical Specifications:
Each element (fuel, reflector) was raised to approximately 10 feet below the pool water level. Visually inspected for cracks and corrosion. The reflectors were rotated 180 degrees. All element
, swelling numbers were verified. Results were entered in the reactor log book Blade worth determinations, using the InHour rnethod, were conducted during 9/22/95 thru 9/26/95. Blade
- 1 was compensated with blade #3; blades #2 and #4 were at full out positions. Blade #2 was compensated with blade #4; blades #1 and #3 were at full out positions.
It was noted that the excess of 1.27% is not enough to overcome xenon during the second morning of operation. The negative Inhour determinations. Therefore, a second set of c e
This established the core excess at 1.7% which is j
i needed to overcome xenon for our type of operation ( l shift per day).
Note:
The operating procedures will be changed to require the operation of the primary pump during InHour determinations.
The new blade worths are as follows:
Blade 1 2.20 %
(
Blade 2 2.05 %
l Blade 3 2.20 %
DEC-5-96 THU 14:50 R 1 NUCLEAR SCIENCE CTR ] A l10 Khode Island Nuclear Science Center
,,u Blade 4 2.25 %
Total:
8.70 %
i The followin compliance: g Technical Specifications were checked to insure l
T.S. 3.0 Limiting Conditions for Operations Specifications:
3.1 Reactivity Limits
- 1. Tha shutdown margin relative to the reference core condition shall be at least 1.0% AK/K with the most reactive shim safety blade and the regulating blade fully withdrawn. (Determined annually).
S/D margin (cold / clean) =
6.71 %
w/ Blade #4 full out position =
2.25%
w/ Reg Rod full out position =
0.24 %
Max. Worth of experiments S/D margin =
0.60 %
=
3.62 %
\\
- 2. The overall core excess reactivity including movable experiments shall not exceed 4.7%AK/K. (Determined annually).
Total core exess is the blade worth remaining in the blade (s) when the reactor is at cold / clean critical position Blade positions (reactor critical):
Blade #1 - full out 0.00 %
Blade #2 - full out 0.00 %
Blade #3 - full out 0.00 %
Blade #4 - 10.16" 1.61 %
1.61 %
- 3. The total reactivity worth of all experiments shall not exceed 0.6%dK/K.
The reactivity worth of experiments located outside of the core (rabbit,
\\
incore device, etc) has been determined to be << 0.60% AK/K reactivity worth. The reactivity worth 1
-G@@ M N ggg @gM [p5DyggqpW W eN
L DEC-5-96 THU 14:50 R 1 NUCl. EAR SCIE CE CTR ] Ag NO l
nnoce Island Nuclear Science Center u
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of experiments conducted within the rabbit system ar O.08%AK/K.
e<<
i
- 6. The reactivity worth of the regulating rod shall not exceed 0.6%AK/K.
The reactivity worth of the regulating blade was i
determined to be 0.24% using the InHour method 3.2 Reactor Safety System
- 4. The reactivity insertion rates of individual control regulating blades will not exceed 0.02% AK/K per second and Differential blade curves derived from the Integeral blade worth curves indicate that no individual b regulating blade exceed the limit.
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DEC-5-96 THU 10:34 R I NUCLEAR SCIENCE CTR FAX N0. 4017824201 P.02 l
TATE OF RHODE ISLAND AND PROVIDENCE PLANTATIONS RHODE ISLAND ATOMIC ENERGY COMMISSION Nuclear Science Center i
South Ferry Road Narragansett, R.I. 02882 1197 December 5, 1996 Docket No. 50-193 Mr. Marvin Mendonca, Senior Project Manager Non-Power Reactors, Decommissioning and Environmental Project Directorate Division of Reactor Projects - III/IV/V U. S. Nuclear Regulatory Commission (NRC)
Washington, DC 20555
Dear Mr. Mendonca:
As discussed in our telephone conversation of December i
4, 1996, this letter requests a one time extension of the
{
annual Technical Specification (T,S.)
surveillance periodicity for safety blade testing (T.S. 4.1.1,4.2.8) and reactivity calculations (T.S. 4.2.6, 4.2.7). This testing is due in late December, 1995 under the 15 months limit of T.S.
1.38 (Surveillance Intervals). It is requested that a one month extension be granted to allow this testing to be done in January, 1996.
The reactor was not operated for most of the 1996 calendar year because of extensive primary and secondary work to add another loop and upgrade primary and secondary pumps. As a result, there is a large backlog of work to be completed that requires reactor operation this month.
Additionally, a new reactor supervisor has been hired and will report in the beginning of January. It is important that he see rod testing and reactivity calculations in order to qualify Senior Reactor Operator. Delaying these tests a month will provide vital training while eliminating the need to do another full set of rod testing early next year. The rod control system and the blades have been operating properly since return to operation in September. This request was reviewed by the Reactor Utilization Committee on December 4, 1996 and the decision was made to request this extension.
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DEC-5-96 THU 10:35 R I NUCLEAR SCIENCE CTR FAX NO 4017824201 P. 03
'Mr. Marvin Mendonca o
December 5, 1996 Page 2 Si
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Terry ehan Direc or TT:cd Copy to:
T. Dragoon, Region One Reactor Utilization Committee l
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