ML20248H727
| ML20248H727 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/05/1989 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20248H722 | List: |
| References | |
| NUDOCS 8910120038 | |
| Download: ML20248H727 (11) | |
Text
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ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-89-36) l LIST OF AFFECTED PAGES Unit 1 3/4 2-17 3/4 3-5 Unit 2 3/4 2-15 3/4 3-5 f
8910120038 891005 PDR ADOCK 05000327 p PDC
= . .
POWER DISTRIBUTION LIMITS
- ACTION
- (Continued).
- 2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range Neutron Flux-High Trip Setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
l
- 3. Identify and correct the cause of the out of limit condit' ion
prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least-once per hour for 12' hours or until verified 'at 95% or greater RATED THERMAL POWER. .,
dg ~ The provisions of Specification 3.0.4 are not applicable.
FP SURVEILLANCE REQUIREMENTS f
4.2.4.1 The QUADRANT' POWER TILT RATIO shall be determined to be within the FP
. limit above 50% of RATED THERMAL POWER by:
- a. Calculating the ratio at least once per 7 days when the al&rm is OPERABLE.
y b. Calculating the ratio at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during steady state operation when the alarm is inoperable.
4.2.4.2 The QUA.DRANT POWER TILT. RATIO shall be determined to be within the limit when above 75 percent of RATED THERMAL POWER with on.e Power Range Channel inoperable by using the movable incore detectors to confirm that the yp normalized symmetric power distribution, obtained from the 4 pairs of symmetric thimble locations ,is consistent with the indicated QUADRANT POWER TILT RATIO at least once per. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
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EQUOYAH - UNIT 1 3/4 2-17
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, y e TABLE 3.3-1 (Continued)
TABLE NOTATION A
With the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal, and fuel in the reactor vessel.
The channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped condition.
The provisions of Specification 3.0.4 ar'e not applicable.
High voltage to detector may be de-energized above the P-6 (Block of Source Range Reactor Trip) setpoint.
ACTION STATEMENTS
~
ACTION 1 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the reactor trip breakers.
ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed provided the following conditions are satisfied:
- a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. ,
lR51
- b. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> lR51 for surveillance testing per Specification 4.3.1.1.1.
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September 17, 1986 SEQUOYAH - UNIT 1 3/4 3-5 Amendment No. 4'7
=
POWER DISTRIBUTION LIMITS
, ACTION: (Continued)
- 2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range Neutron Flux-High _.
3 Trip Setpoints to less than or equal to 55% of RATED THER?tAL -
POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- 3. Identify and correct the*cause of the out of limit condition prior to increasing THERMAL POWER; subsequent. POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until verified at 95% or greater RATED THERMAL POWER.
h The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.2.4.1 The QUADRANT POWER TILT RATIO shall be determined to be within the limit above 50% of RATED THERMAL POWER by:
- a. Calculating the ratio at least once per 7 days when the alarm is OPERABLE.
- b. Calculating the ratio at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during steady state operation when the alarm is inoperable.
4.2.4.2 The QUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75 percent of RATED THERMAL POWER wits one Power Range channel inoperable by using the movable incore detectors.to confirm that the normalized
, symmetric power distribution, obtained from 4 pairs of symmetric thimble locationsMs consistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. -
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1 TABLE 3.3-1 (Continued) !
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l TABLE NOTATION A
With the reactor trip system breakers in the closed position, the \
i control rod drive system capable of rod withdrawal, and fuel in the !
reactor vessel.
l The channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped l
condition.
The provisions of Specification 3.0.4 are not applicable.
High voltage to detector may be de-energized above the P-6 (Block of Source Range Reactor Trip) setpoint.
ACTION STATEMENTS I
"' ACTION 1.- With the number of OPERABLE channels one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the reactor trip breakers.
ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
- a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. lR39
- b. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> lR39 for surveillance testing per Specification 4 3.1.1.1.
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l l September 17, 1986 SEQUOYAH - UNIT 2 3/4 3-5 Amendment No. 39
8 y a ENCLOSURE 2 PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-89-36) DESCRIPTION AND JUSTIFICATION FOR CLARIFICATION OF ACTION REQUIREMENTS FOR QUADRANT POWER TILT RATIO MONITORING
1 ENCLOSURE 2 - Description of Change Tennessee Valley Authority proposes to modify the Sequoyah Nuclear Plant (SQN) Units 1 and 2 technical specifications (TSs) to revise the action statements i for quadrant power tilt ratio monitoring and power range instrumentation to provide a consistent set of actions to be taken when the quadrant power tilt
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ratio is not monitored or confirmed in accordance with either Surveillance Requirement (SR) 4.2.4.1 or 4.2.4.2. Reason for Change An NRC resident inspector identified the possibility of multiple
' interpretations for the actions to be taken when the quadrant power tilt ratio is not monitored or confirmed in accordance with SRs 4.2.4.1 and 4.2.4.2.
This condition was identified to TVA on July 26, 1989. TVA evaluated the situation and confirmed that the SQN TSs are in general conformance with NRC's standard TSs. TVA further evaluated the situation and identified that TS 3.2.4 does not contain specific actions to address the situation when either SR 4.2.4.1 or 4.2.4.2 cannot be performed in the timeframe specified. Possible
. interpretations to determine action timeframes can lead to the application of TS 3.0.3 or the most limiting action in TS 3.2.4. The final power level is not clearly specified. Possible interpretation on final power level can include power levels below which TS 3.2.4 is not applicable or power levels below which the individual SR is not applicable.
TVA also evaluated Action 2 in Table 3.3-1 for multiple interpretations. Action 2.d appears to be redundant to SR 4.2.4.2. Action 2.c has two options to perform, one of which appears to apply different requirements than 2.d when reactor power is below 75 percent. Action 2.c has also been interpreted by the NRC resident inspector to require power reduction and recalibration within 4 hours when Action 2.d cannot be met. TVA has interpreted the TSs that TS 3.0.3 applies when Action 2.d cannot be met because none of the conditions in Action 2 specifically address the situation. This interpretation is based on consideration of the specific wording in Action 2.c (the use of
" restricted") as meaning something different from the wording in similar actions for TS 3.2.4 (the use of " reduce"). In addition, similar actions in TS 3.2.4 specify separate times for power reduction and recalibration while Action 2.c appears to assume that power is already at or below 75 percent.
Change SR 4.2.4.2 to allow the use of a full core map to confirm power distribution will preclude an unnecessary plant derating in the event one of the thimbles, comprising the four symmetric pairs, becomes inoperable. l l Justification for Change New action statements are proposed for TS 3.2.4 to specifically address the situations when SRs 4.2.4.1 and 4.2.4.2 cannot be performed in the timeframe specified. The action statements apply any time the SRs cannot be performed,
< is . ., . 1 regardless of the cause. The new action statements have specific timeframes for, power reduction consistent with TS 3.0.3. .The new action statements have specific power levels consistent with the power levels specified in the applicability section of.TS 3.2.4 SR 4.2.4.2, and Action 2.c of Table 3.3-1.
". The new action statement for SR 4.2.4.1 has recalibration timeframes consistent with the other action statements in TS 3.2.4 and Action 2.c of Table 3.3-1. This new action statement also has recalibration setpoints consistent with the setpoints in Action 2.c of Table 3.3-1 and actions to be 'I taken.when recalibration cannot be accomplished as specified. !
The new action statements have repair times specified that are longer;than the other action statements in TS 3.2.4. This difference is appropriate because the other action statements in TS 3.2.4 apply for the cases where the quadrant power tilt ratio is out of limits, a situation that needs a quick remedy. The proposed' action statements for TS 3.2.4 apply for the cases where only monitoring capability is affected. TVA believes that it is prudent to provide sufficient repair time for a loss of monitoring capability to provide a reasonable opportunity to remedy the situation before requiring that a plant transient be introduced. In the absence of any immediate safety issue (e.g., out-of-limit conditions), repairs should be considered before initiating any plant transient that could evolve into a more severe condition if problems occur. The proposed action statements provide clear guidance to the operator that is consistent with present requirements but in a more user-friendly format. It eliminates the need to apply TS 4.0.3 when SRs 4.2.4.1 or 4.2.4.2 cannot be performed as required. . It eliminates the need to recognize that none of the current actions in TS 3.2.4 apply, and consequently the requirements of TS 3.0.3 must be followed. It eliminates the need to recognize that the requirements of TS 3.0.3 are satisfied when power is reduced such that SR 4.2.4.2 no longe applies or that Action 2.c of Table 3.3-1 is met. 3 i A revision to Action 2 of Table 3.3-1 is proposed to eliminate requirements that are redundant to SRs 4.2.4.1 and 4.2.4.2 and the new proposed action statements described above. Action 2.d is deleted because it is redundant to SR 4.2.4.2. Action 2.c is revised to delete information that more
. appropriately belongs in TS 3.2.4 since it contains remedial actions for quadrant power tilt ratio requirements. The information deleted has been included in the proposed action statements for TS 3.2.4. Action 2.c will now simply direct the operator to TS 3.2.4 for quadrant power tilt ratio monitoring. TS 3.2.4, as modified, contains all SRs and remedial actions
-related to quadrant power tilt ratio monitoring.
Addition of the option of using a full core map to verify normalized power distribution meets the intent of the original SR 4.2.4.2. A full core map using the incore novable detectors will provide information pertaining to quadrant power tilt ratio that is equivalent to that obtained using the four pairs of symmetric thimbles. I
g' . p . u ; .; Environmental Impact Evaluation
- j. The proposed change request does not involve an unreviewed environmental question because operation of SQN Units 1 and 2 in accordance with this change would.not:
- 1. Result in asignificant increase in any adverse environmental impact ;
previously evaluated in the Final Environmental Statement (FES) as- l modified by the Staff's testimony to the Atomic Safety and Licensing l
. Board,' supplements to the FES, environmental impact appraisals, or in any decisions of'the Atomic Safety and Licensing Board.
l'
- 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. ;
s .. l. t I l l c i
- - _ _ - - - _ _ _ _ _ _ - _ _ . ._ __ ___ _ a
9 0 1 ENCLOSURE 3 PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-89-36) DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATIONS J l
.~ __ _-__
F ENCLOSURE 3 Significant Hazards Evaluation TVA has evaluated the proposed TS change and has determined 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 proposed amendment will not:
- 1. Involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed revisions to the action statements for TS 3.2.4, " Quadrant Power Tilt Ratio," and Action 2 of Table 3.3-1 for the reactor trip system power range channels are simply a reformatting of existing requirements in a user-friendly format to eliminate the potential for misinterpretation. Use of a full core map to confirm normalized power distribution provides information pertaining to quadrant power tilt ratio that is equivalent to that obtained using the four pairs of symmetric thimbles. These changes have no impact on the probability or consequences of an accident previously evaluated.
- 2. Create the possibility of a new or different kind of accident from any previously analyzed. ]
The proposed revisions to the action statements for.TS:3.2.4, " Quadrant i Power Tilt Ratio," and Action 2 of Table 3.3-1 for the reactor trip system power range channels are simply a reformatting of existing requirements in a user-friendly format to eliminate the potential for misinterpretation. Use of a full core map to confirm normalized power distribution provides information pertaining to quadrant power tilt ratio that is equivalent to that obtained using the four pairs of symmetric thimbles. These changes do not create the possibility of a new or different kind of accident from any previously analyzed.
.3. Involve a significant reduction in a margin of safety.
The proposed revisions to the action statements for TS 3.2.4, " Quadrant Power Tilt Ratio," and Action 2 of Table 3.3-1 for the reactor trip system power range channels are simply a reformatting of existing requirements in a user-friendly format to eliminate the potential for misinterpretation. Use of a full core map to confirm normalized power distribution provides information pertaining to quadrant power tilt ratio that is equivalent to that obtained using the four pairs of symmetric thimbles. These changes do not involve a reduction in any margin of safety.
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