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Proposed Tech Specs Revising Section 3/4.10.3,defining Testing Necessary for Consistency Between Limiting Condition for Operation & Surveillance Requirements
	ML20006E240
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Site:	Sequoyah
Issue date:	02/14/1990
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-SPECIAL TEST EXCEPTIONS 3/4.10.3 PHYSICS TESTS L

LIMITING CONDITION FOR OPERATION 3.10.3 The limitations of Specifications 3.1.1. 3, 3.1.1. 4, 3.1. 3.1, 3.1. 3. 5 and 3.1.3.6 may be suspended during the performance of PHYSICS TESTS provided:

The THERMAL POWER does not exceed 5% of RATED THERM /.L POWER, a.

b.

The reactor trip setpoints on the OPERABLE Intermediate and Power Range Nuclear Channels low trip setpoints are set at less than ur equal to 25% of RATED THERMAL POWER, and g

The Reactor Coolant System lowest operating loop temperature (T c.

is greater than or equal to 531*F.

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APPLICABILITY: MODE 2.

. ACTION:

With the THERMAL POWER greater than 5% of RATED THERMAL POWER, a.

immediately open the reactor trip breakers.

b.

With a Reactor Coolant System operating loop temperature (T,yg than 531*F, restore T to within its limits within 15 minutes or av9 be in at least HOT STANOBY within the next 15 minutes.

SURVEILLANCE REQUIREMENTS 4.10 3.1 of RATED. THERMAL POWER at least once per hour during PHYS 4.10.3.2 Each Intermediate and Power Range Channel shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to initiating PHYSICS TESTS.

'4.10.3.3 The' Reactor Coolant System temperature (T,yg) shall be determined to be greater than or equal to 531*F at least once per 30 minutes during PHYSICS TESTS.

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SEQUOYAH - UNIT 1 3/4 10-3

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3/4.10 SPECIAL TEST EXCEPTIONS BASES 3/4.10.1 SHUTolvil PARGIN This special test exception provides that a minieum 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 reouired to permit the periodic verification of the actual versus predicted core reactivity condition occurrino as a result of fuel burnup or fuel cycling operations.

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3/A.10.2 GROUP HEIGHT, INSERTION, AND POWEP DISTRIBUTION LIMITS Tiis special test exception permits individual control rods to be positio}ned outside of their nomal oroup heights and insertion limits durina the performance of such PHYSICS TESTS as those reauired to 1) measure control rod worth and 2) detemine the reactor stability index and danping factor under xenon oscillation conditions.

3/a.10.3 PHYSICS TESTS This special test exceotion oemits DHYSICS TF.STS to Fe nerfomed at less than or eoual-to 5% of PATED THEPPAL P0ldEP with the PCS T slichtly lower than nonnally allowed so that the fundarental nuclear cha$teristics 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 reasure the roderator temperature coefficient at POL it is necessary to position various control rods at heiahts which ray not normally be allowed by Specification 3.1.3.6 which ray cause the PCS T slightly below the minimum temperature of Specification 3.1.1Np' to fall 3/4.10.4 DEACTOR COOLANT LOOPS This scecial test exception pemits reactor criticality under no flow

. conditions and is recuired to Derfonn certain startup and PHYSICS TESTS while at low THEP!'AL POWP levels.

3/4 10.5 POSITION INDICATI0F SYSTEP-SPUTODUM This soecial test exception oemits the rosition indication sv: vs to be 1

inoperable during rod drop time measurements. The exception is reouired since the data necessary to determine the rod drop tire is derived ' rom the induced voltaae in the position indicator coils as the rod is-drooped.

This induced voltaae is small comoared to the nomal voltaae and, therefore, can not he observed if the position indication systems remain OPEDAPLF.

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3/4.10 SPECIAL TEST EXCEPTIONS

-BASES 3/4'.10.I SHUTOOWN 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 occuring 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) determi'ne 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 lower than normally allowe'd so that the fundamental nuclear chaN8teristics 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 mcderator temnerature coefficient at BOL, it. is necessary to position the various controi rods at heights which may not normally be allowed by Specification 3.1.3.6 which in turn may cause the RCS T,y9 to fall slightly below the minimum temperature of Specification 3.1.1.4.

t 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 in the position indicator coils as the rod is dropped.

This induced voltage is small compared to the normal voltage and, therefore, can not be observed if the position indication systems remain OPERABLE.

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2 ENCLOSURE 2

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TECHNICAL SPECIFICATION BASES CHANGE-

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a DESCRIPTION AND JUSTIFICATION FOR-'

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REVISING BASES SECTION 3/4.10.3 l

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ENCLOSURE 2

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_l Description of Chang Tennessee Valley Authority is modifying the Sequoyah Nuclea.- Plant (SQN)

Unita 1 and 2 Technical Specifications (TSs) Bases Section 3/4.10.3 to accurately define the testing requirements'of Surveillance Requirement (SR) 4.10.3.2.

This material is being provided to NRC for information purposes.

Reason and Justification for Change Limiting Condition for Operation (LCO) 3.10.3.b_ requires that for the performance of low power physics testi.ng (pursuant to TS 3/4.10.3), the intermediate and power range low reactor trip setpoints must be set at less than or equal to 25 percent rated thermal power. SR 4.10.3.2 requirds that channel functional tests be performed on the intermediate and power-range channels within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of initiating physics testing.

The revision to Bases Section 3/4.10.3 is made to define that for

onsistency between LCO 3.10.3.b and SR 4.10.3.2, only the intermediate and power range low setpoint reactor trip functions, operating at less than or equal to 25 percent rated thermal power, need to be functionally tested for the performance of physics testing. The functional test of these trips within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of initiating physics testing provides an additional amount of assurance that the low power reactor trips are available to limit power excursions during the physics tests.

Operability of all intermediate and power range functions is demonstrated prior to entry into Mode 2 in accordance with TSs 2.2.1 and 3/4 3.1.

Environmental Impact Evaluation The bases change does not involve an unrevi.wed environmental question because operation of SQN Units 1 and 2 in accordance with this change, would not:-

1.

Result in a significant increase in any adverse environmental impact previously evaluated in the Final Environmental Statement (FES) as modified by the Staff's testimony to the Atomic Safety _and Licensing Board, supplements to the FES, environmental impact appraisals, or decisions of the Atomic Safety and Licensing Board.

2.

Result in a significant change in effluents or power levels.

3.

Result in matters not previously reviewed in the licensing basis for

-SQN that may have a significant environmental impact.

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TECHNICAL SPECIFICATION BASES CHANGE

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- DETERMINATION OF KO SIGNIFICANT HAZARDS CONSIDERATIONS 4

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ENCLOSURE 3 Significant Hazards Evaluation TVA has evaluated the TS bases change and has determir.e6 that it does not represent a significant hazards consideration based on criteria established in 10 CFR 50.92(c). Operation of SQN in accordance with the change will not:

(1) Involve a significant increase in the probability or consequences of an accident previously evaluated.

The LCOs of TF 3.10.3 ensure that reactor core parameters are maintained wi.hin acceptable limits during the performance of low po'wer physics testing. LCO 3.10.3.b specifically requires the intermediate and power range low reactor trip setpoints to be set at less than or equal to 25 percent rated thermal powe-The bases revision does not alter this requirement.

Tb1 change merely clarifies that testing performed for SR 4.10.3.2 verifies the operability of the functions required by LCO 3.10.3.b.

Because the requirements of LCO 3.10.3 remain unchanged and will continue to be met by the performance of surveillance testing, the bases change will not increase the probability or consequences of a previously evaluated accident.

(2) Create the possibility of a new or dif ferent kind. of. accident f rom any previously analyzed.

The bases change is made to provide consistency between the requirements of LCO 3.10.3.b and SR 4.10.3.2.

There are no changes to the design, method of operation, or physics testing methods. As such, the possibility of a new or different accident from those l

previously analyzed is not created.

(3) Involve a significant reduction in a margin of safety.

L As described above, the change made to Bases Section 3/4.10.3 is made to clearly define the testing necessary to ensure that the requirements of LCO 3.10.3.b are satisfied. Because the requirements of LCO 3.10.3 remain unchanged and will continue to be verified by i

surveillance testing, the controls on reactor core parameters in l

effect during low power physics testing remain unchanged, and there is no reduction in the margin of safety.

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ML20006E240

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