ML20042G107
| ML20042G107 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/01/1990 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | Kingsley O TENNESSEE VALLEY AUTHORITY |
| Shared Package | |
| ML20042G108 | List: |
| References | |
| TAC-76076, TAC-76077, NUDOCS 9005110103 | |
| Download: ML20042G107 (7) | |
Text
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May 1. 1990 Docket Nos.'50 327 Reissued to include original copy of TS pages.
and 50 328 Any questions call Ardel, X20795 l
l Mr. Oliver D. Kingsley, Jr.
j Senior Vice President, Nuclear Power Tennessee Valley Authority j
6N 38A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402 2801 3
Dear Mr. Kingsley:
SUBJECT:
LOW POWER PHYSICS TESTS FOR SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 (TACS76076/76077)(TS89-07)
Enclosed are changes to the Bases pages for Section 3/4.10.3, Physics Tests, of the Sequoyah Nuclear Plant, Units 1 and 2. Technical Specifications (TSs).
The change for each unit adds text to the TS Bases explaining that the testing required by Surveillance Requirement (SR) 4.10.3.2 is to ensure that the inter.
mediate and power range trip functions which operate at less than or equal to 25% of rated thermal power are operable.
The revised TS Bases clarify the requirements in SR 4.10.3.2 and explain the consistency between Limiting Condition for Operation 3.10.3.b and SR 4.10.3.2.
This is based on the enclosed Safety Evaluation.
Tiiese changes are net amendments to the licensu.for Unit:; I and 2.
In a:cordance with 10 CFR 60.36(a), the TS Bases include statc;nents on the bases or reasons for specifications ir, the TSs, bt they ars net prt of the Ms or the licente.
Sincerely, Original Signed by Suzanne Black, Assiscar.t Director for Projects TVA Projects Divi 41on Office of Ncclear Reactor Regulation
Enclosures:
1.
Bases Change for Sequoyah, Unit 1 2.
Bases Change for Sequoyah, Unit 2
-3.
Safety Evaluation
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Document Name:
SEQUOYAH TACS 76076/77 7
9005110103 900501 I
PDR ADOCK 05000327 M
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.c Mr. Oliver D. Kingsley, Jr.,
cc:
Mr. Marvin Runyon, Chairman Mr. Joseph Bynum, Acting Site Director Tennessee Valley Authority Sequoyah Nuclear Plant ET 12A 7A Tennessee Valley Authority 400 West Sumit Hill Drive P. O. Box 2000 Knoxville, Tennessee 37902 Soddy Daisy, Tennessee 37379 Mr. C. H. Dean, Jr., Director Mr. Mark J. Burzynski Tennessee Vallej Authority Site Licensing Manager ET 12A 11A Sequoyah Nuclear Plant 400 West Summit Hill Drive P. O. Box 2000 Knoxville, Tennessee 37902 Soddy Daisy, Tennessee 37379 Mr. John B. Waters, Director County Judge Tennessee Valley Authority Hamilton County _ Courthouse ET 12A 9A Chattanooga, Tennessee 37402 400 West Sumit Hill Drive Knoxville, Tennessee 37902 Regional Administrator, Region II U.S. Nuclear Regulatory Comission Mr. W. F. Willis 101 Marietta Street, N.W.
Chief Operating Officer Atlanta, Georgia 30323 ET 12B 16B 400 West Summit Hill Drive Mr. Kenneth M. Janison Knoxville, Tennessee 37902 Senior Resicent Inspector Sequoyah tuclear Plant General Counsel U.S. Nu;;lur Regulatory Comission Tennessee Valley Authority 2600 'gou ferry Road 400 West Sumit Hill Drhe
' Soddy Daisy, Ternessee 37379 ET llB 33:1 Knoxville, Tennessee S7002 Mr. Michtel H. MoDiey, Director Division of Radiological Health Mr. Dwight Nunn T.E.R.R. A. Building, 6th Floor Vice President, Nuclear Engineering 150 9th Avenue North Tennessee Valley Authority Nashville, Tennessee 37219-5404 6N 38A Lookout Place 1101 Market Street Dr. Henry Myers, Science Advisor Chattanoogt. Tennessee 37402-2801 Comittee on Interior and Insular Affairs l
Dr. Mark 0. Medford U.S. House of Representatives Vice President and Nuclear Washington, D.C.
20515 Technical Director Tennessee Valley Authority Tennessee Valley Authority 6N-38A Lookout Place Rockville Office Chattanooga, Tennessee 37402-2801 11921 Rockville Pike Suite 402 Mr. Edward G. Wallacs Rockville, Maryland 20852 Manager, Nuclear Licensing and Regulatory Affairs Tennessee Valley Authority SN 157B Lookout Place Chattanooga, Tennessee 37402-2801 i
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, REVISED BASES PAGES FACILITY OPERATING LICENSE NO. OPR-77 DOCKET NO. 50-327 I
Revise the Appendix A Technical Specifications by removing the pages identified i
below and insert!pg the enclosed pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT B'3/4 10-1 B 3/4 10-1 I
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.A.
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,L 3/4.10 SPECIAL TEST EXCEPTIONS BASES p
3/4.10.1 SHUTDOWN MARGIN This special test exception provides that a minimum amount of control rod worth is immediately available for reactivity control when tests are performed for control rod worth measurement.
This special test exception is required to permit the periodic verification of the actual versus predicted core
' reactivity condition occurring as a result of fuel burnup or fuel cycling operations.
3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS This special test exception permits individual control rods to be positioned outside of their normal group heights and insertion limits during the performance of such PHYSICS TESTS as those required to 1) measure control rod worth and 2) determine the t'eactor stability index and damping factor under xenon oscillation conditions.
3/4.10.3 PHYSICS TESTS This special test txception permits PHYSIC $ TE$1S 10 be perfCrned at le59 I
than or equal to 5% of RATED THERMAL POWER with the RCS T slightly ' lower AVC then r.orn4 ally ellowed so that the fundamental nuclear characte>btics of the reactor core and related instru:eentarion can be verified, in cMer for s Jrdous cherecteristics to be accurately titmrod it is, at Umer, necessary to eperate outside the normel restriethos af these technical Specifict.tinnb.
Fot instance, to icesure the moderator temperature coef ficitent at ECL f t is 1
necessary to notition various control rods at heights which may not nermal?y he allowed by Specification 3.1.3.6 which may cause the RCS T tc f aH gyg s' lightly below tt.c minimum temperature of Specification 3.L L4.
Testing performed pursuant tn Specification 4.10.3.2 ensures that the intermediate and power range reactor trip functions which operate at less than or equal to 25% RATED THERMAL POWER are available to limit power excursions during PHYSICS TESTS.
3/4.10.4 REACTOR COOLANT LOOPS This special test exception permits reactor criticality under no flow conditions and is required to perform certain startup and PHYSICS TESTS while at low THERMAL POWER levels.
i 3/4 10.S POSITION INDICATION SYSTEM-SHUTDOWN This special test exception permits the position indication system to be inoperable during rod drop time measurements.
The exception is required since the data necessary to determine the rod drop time is derived from the induced voltage in the position indicator coils as the rod is dropped.
This induced j
voltage is small compared to the normal voltage and, therefore, can not be observed if the position indication systems remain OPERABLE.
l SEQUOYAH - UNIT 1 B 3/4 10-1 Revised: 05/01/90 I
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,j ? 'X REVISED BASES PAGES 9i-FACILITY OPERATING LICENSE N0. DPR-79 DOCKET NO. 50-328 Revise the Appendix A Technical Specifications by removing the pages identified below and~ inserting-the enclosed pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area
- of change.
REMOVE INSERT B 3/4 10-1 B 3/4 10-1 I
a j:
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3/4.10 SPECIAL TEST EXCEPTIONS BASES 3/4.10.1 SHUT 00WN MARGIN This special test exception provides that a minimum amount of control rod worth is immediately available for reactivity control when tests are performed for control rod worth measurement.
This special test exception is required to permit the periodic verification of the actual versus predicted core reactivity' condition occurring as a result of fuel burnup or fuel cycling operations.
3/4.10.2 GROUP ~ HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS This special test exception permits individual control rods to be positioned outside of their normal group heights and insertion limits during the performance of such PHYSICS TESTS as those required to 1) measure control rod worth and 2) determine the reactor stability index and damping factor under xenon oscillation conditions.
3/4.10.3 PHYSICS TESTS This special test exception permits PHYSICS TESTS to be performed at less than or equal to 5% of RATED THERMAL POWER with the RCS T slightly 1cwer AVG than normally allowed so that the fundamental nuclear characteristics of the reactor core and related instrumentation can be verified.
In order for various characteristics to be accurately measured it is, at times, necessary to operate outside the normal restrictions of these technical Specifications.
For instance, to measure the moderator temperature coefficient at BOL it is necessary to position various control rods at heights which may not normally be allowed by Specification 3.1.3.6 which may cause the RCS TAVG.to fall slightly below the minimum temperature of Specification 3.1.1.4.
Testing performed pursuant to Specification 4.10.3.2 ensures that the intermediate and power range reactor trip functions which operate at less than or equal to 25% RATED THERMAL POWER are available to limit power excursions during PHYSICS TESTS.
J 3/4.10.4 REACTOR COOLANT LOOPS This special test exception permits reactor criticality under no flow conditions and is required to perform certain startup and PHYSICS TESTS while
.at low THERMAL POWER levels.
3/4 10.5 POSITION INDICATION SYSTEM-SHUTDOWN This special test exception permits the position indication systems to be
~ inoperable during rod drop time measurements.
The exception is required since the data necessary to determine the rod drop time is derived from the induced
. voltage.
the position indicate coils as the rod is dropped.
This induced voltage is small compared to tv normal voltage and, therefore, can not be observed if the position indication systems remain OPERABLE.
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- SEQUOYAH - UNIT 2 B 3/4 10-1 Revised: 05/01/90 4
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DATED:
May 1 '1990' DISTRIBUTION:
- Docket File NRC'PDR' Local PDR
. SQN Reading ADSP Reading DCrutchfield
' BDLiaw SBlack Licensing (Assistant JDonohew 2)
RPierson.
BWilson, Region II LWatson, Region II
' BGrimer.
9-A-2) 1 EJordan MNBB-3701) 1 DHagan MNBB-3206)
TMeek(8)
(P1-37)
- WJones P-522) l LJCalvo-11-F-23)
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' ACRS(10).
P-315)
GPA/PA 2-G-5)
GPA/CA 17-A-3)
- ARM /LFMB (MNBB-4503)
OGC.
(15-B-18)
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