ML20217P814

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Proposed Tech Specs Re Upper Tubesheet Volumetric Indications to Remain in Svc for Cycle 15
ML20217P814
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 04/01/1998
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20217P792 List:
References
NUDOCS 9804100201
Download: ML20217P814 (5)
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Text

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3.1.6 Leskrga Specification

  • 3.1.'.1 6

If the total reactor coolant leakage rate exceeds 10 gpm, the

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reactor shall be shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of detection.

3.1.6.2 If unidentified reactor coolant leakage (exceeding normal evaporative losses) exceeds 1 gpm or if any reactor coolant leakage is evaluated as unsafe, the reactor shall be shut-down within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of detection.

3.1.6.3.a If it is determined that any reactor coolant leakage exists through a non-isolable fault in a reactor coolant system strength boundary (such as the reactor vessel, piping, valve body, etc., except steam generator tubes), the reactor shall be shutdown and a cooldown to the cold shutdown condition shall be initiated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of detection.

3.1.6.3.b If the leakage through the tubes of any one steam generator equals or exceeds 150 gallons per day (0.104 gpm), a reactor l shutdown shall be initiated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and the reactor shall be in the cold shutdown condition within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

I 3.1.6.4 Deleted 3.1.6.5 Action to evaluate the safety implication of reactor coolant leakage shall be initiated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of detection. The nature, as well as the magnitude of the leak, shall be

! considered in this evaluation. The safety evaluation shall

(asure that the exposure of offsite personnel to radiation is l stithin the guidelines of 10CFR20.

i l 3.1.6.6 If reactor shutdown is required per Specification 3.1.6.1, l 3.1.6.2, or 3.1.6.3 the reactor shall not be restarted until i the leak is repaired or until the problem is otherwise l corrected.

3.1.6.7 when the reactor is at power operation, three reactor cool-ant leak detection systems of different operating principles j shall be in operation. One of these systems is sensitive to i

radioactivity and consists of a radioactive gas detector ar.d an air particulate activity detector. Both of these instru-i ments may be out-of-service simultaneously for a period of no more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided two other means are available to detect leakage and reactor building air samples are taken and analyzed in the laboratory at least once per shift; other-wise, be in at least 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 in Cold Shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

3.1.6.8 Loss of reactor coolant through reactor coolant pump seals and system valves to connecting systems which 9804100201 980401 PDR ADOCK 050003 3 P

Amendment No, M,M4,M4,M4,MG, 27 g

8. Un7orvictrble daccribas tha condition of a tuba if it laska or contcins a dafset 1crga enough to cffset its ctructurel ,

intsgrity in th2 sysnt of cn Op3rcting Basic Earthqunks, n  !

loss-of-coolant accident, or a steam line or feedwater line break as specified in Specification 4.18.4.c.

9. Tube Inspection means an inspection of the steam generator

. tube from the point of entry completely to the point of exit. For tubes that have been repaired by the reroll process within the upper tubesheet, that portion of the tube above the new roll can be excluded from future periodic inspection requirements because it is no longer part of the pressure l boundary once the repair roll is installed.

b. The steam generator shall be determined operable after completing the corresponding actions (plug, reroll, or sleeve all tubes l exceeding the plugging limit and all tubes containing through-wall l cracks) required by Table 4.18-2 with the following exception:

Tubes with outer diameter intergranular attack indications within the upper tubesheet with potential of through-wall depths greater than the plugging limit, located by eddy current between 2.75 inches above the secondary face and below the roll transition, may remain in service for Cycle 15 contingent upon the following conditions:

1. One hundred percent of the unsleeved tubes are examined by bobbin coil eddy current in the upper tubesheet region during the fourteenth refueling outage,
2. Bobbin coil indications in the upper tubesheet region are examined by rotating pancake coil eddy current and confirmed to be volumetric, l
3. A comparison shall be nade between the bobbin coil voltage measured during the thirteenth refueling outage for the confirmed indications and the bobbin coil voltage for the same indications measured during the fourteenth refueling outage.

The comparison shall confirm essentially no increase in voltage on average, and I

4. In-situ pressure testing in the "A" steam generator during the fourteenth refueling outage confirms, at a 95% confidence level, that the bounding accident leakage due to volumetric ODIGA flaws within the upper tubesheet region will be less than 0.5 gallon per minute due to a main steam line break.

4.18.6 Reports Following each inservice inspection of steam generator tubes, the l

complete results of the inspection shall be reported to the NRC. This report, to be submitted within 45 days of inspection completion, shall j include l a. Number and extent of tubes inspected; l 1

l

b. Location and percent of wall-thickness penetration for each indication of an imperfection;
c. Identification of tubes plugged and tubes sleeved; and
d. Number of tubes repaired by rerolling and number of indications detected in the new roll area of the repaired tubes.

This report shall be in addition to a Special Report (per Specification 6.12.5.d) required for the results of steam generator tube inspections which fall into Category C-3 as denoted in Table 4.18-2. The Commission shall be notified of the results of steam generator tube inspections which fall into Category C-3 prior to resumption of plant operation. The written Special Report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.

Amendment No. 34,44,M,M6,M4,M9, 11Om1

a.

4 I

l l

l l

t 1

MARKUP OF CURRENT ANO-1 TECHNICAL SPECIFICATIONS (For Information Only Asaming Prior Approval ofRepair Roll Change) l l

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a

. 3.1.6 Leakage l Specification  ;

. 3.128.1 If the total reactor coolant leakage rate exceeds 10 gpm, the reactor shall be shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of detection.

3.1.6.2 If unidentified reactor coolant leakage (exceeding nornal evaporative losses) exceeds 1 gpm or if any reactor coolant j leakage is evaluated as unsafe, the reactor shall be shut- )

down within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of detection. }

3.1.6.3.a If it is determined that any reactor coolant leakage exists through a non-isolable fault in a reactor coolant system strength boundary (such as the reactor vessel, piping, valve body, etc., except steam generator tubes), the reactor shall be shutdown and a cooldown to the cold shutdown condition shall be initiated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of detection.

1 3.1.6.b.b If the leakage through the tubes of any one steam generator f equals or exceeds JJ,2 6GO-gallons per day (0 3 447 gpm)*, a l j reactor shutdown shall be initiated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and the reactor shall be in the cold shutdown condition within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

This limit 4;; been ::du;;d to lit gallen: p: day (0.1 spa) 4: th ::= i=d:: : cycle it.

3.1.6.4 Deleted 3.1.6.5 Action to evaluate the safety implication of reactor coolant leakage shall be initiated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of detection. The nature, as well as the magnitude of the leak, shall be considered in this evaluation. The safety evaluation shall assure that the exposure of offsite personnel to radiation is within the guidelines of 10CFR20.

3.1.6.6 If reactor shutdown is required per Specification 3.1.6.1, 3.1.6.2, or 3.1.6.3 the reactor shall not be restarted until the leak is repaired or until the problem is otherwise j corrected. 1 1

3.1.6.7 When the reactor is at power operation, three reactor cool- I ant leak detection systems of different operating principles shall be in operation. One of these systems is sensitive to radioactivity and consists of a radioactive gas detector and an air particulate activity detector. Both of these instru-ments may be out-of-service simultaneously for a period of no more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided two other means are available to detect leakage and reactor building air samples are taken and analyzed in the laboratory at least once per shifts other-wise, be in at least 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 in Cold Shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

3.1.6.8 Loss of reactor coolant through reactor coolant pump seals and system valves to connecting systems which Amendment No. 67,M6,MS,4% M9, 27

M

. 8. Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in Specification 4.18.4.c.

9. Tube Inspection means an inspection of the steam generator tube from the point of entry completely to the point of exit.
b. The steam generator shall be deterndned operable af ter completing the corresponding actions (plug or sleeve all tubes exceeding the l

plugging limit and all tubes containing through-wall cracks) I l

required by Table 4.18-2 with the followins exceptions ,

Tubes with outer di===ter interaranular attack indicgpions within the

! usoer tubesheet with notential of throuah-wall depths areater than  :

t 3e cluaaina limit, located by eddy current between 2.75 inches above t se secondarv face and be:.ow the roll trans:. tion, may remain in j service for Cvele 15 cont:.naent upon the fo:.lowina conditions:

1. One hundred narcent of the unsleeved tubes are ex==4ned by bobbin coil ecidv current in the unoer tubesheet reaion durina j the fourteenth refuelina outaae,
2. Bobbin coil indications in the unoer tubesheet reaion are examined by rotatinc cancake coil eddy current and confirmed to be volumetric, l 3. A comparison shall be made between the bobbin coil voltaae

! measured durina the thirteenth refuelina outaae for the confirmed indications and the bobbin coil voltaae for the s33g indications measured durina the fourteenth refuelina outaae.

The comparison shall confirm epsentially no increase in voltaae on averace, and l

4. In-situ cressure testina in the "A" steam aenerator durina the f staae confima, at a 95% condidence level, that the boundina accident lea caae due to volumetr:.c ODIGA flaws within the unoer tubesheet reaion will be less than 0.5 aallon Der minute due to a main steam line break.

4.18.6 Reports Following each inservice inspection of steam generator tubes, the complete results of the inspection shall be reported to the NRC. This report, to be submitted within 45 days of inspection completion, shall include:

I

a. Number and extent of tubes inspected;
b. Location and percent of wall-thickness penetration for each  !

indication of an imperfection; j

c. Identification of tubes plugged and tubes sleeved; and
d. Number of tubes repaired by rerolling and number of indications detected in the new roll area of the repaired tubes.

This report shall be in addition to a Special Report (per Specification 6.12.5.d) required for the results of steam generator tube inspections which fall into Category C-3 as denoted ir, Table 4.18-2. The Commission shall be notified of the results of steam generator tube inspections which fall into Category C-3 prior to resumption of plant operation. The written Special Report shall provide a description of investigations conducted to deterudne cause of the tube degradation and corrective measures taken to prevent recurionce.

Amendment No. 34,64,M,MG,M4,M9, 11Oml

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