ML20117P292

Proposed Tech Specs Clarifying Requesting Administrative Change to Unit 2 TSs Deleting Ref to cycle- Specific L* Criteria

ML20117P292
Person / Time
Site:	Farley
Issue date:	09/16/1996
From:	SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20117P288	List: ML20117P286 ML20117P292
References
NUDOCS 9609230035
Download: ML20117P292 (56)

Text

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Attachment 1 I l

Unit 2 Technical Specification Pages ,

l for l Voltage-Based Repair Criteria l

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l Unit 2 Technical Specification Page Markups I l

1 for Voltage-Based Repair Criteria l l

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5th;T*3 1 * *.):. * $ f tide i

! 5 ".* A*.'t : *. ANCE PE U:pctLw*s *anu n.eet i

i 2 fees na these stess where espettence has indicated '

potentsat prettens.

3. At least 36 of the total number of sleeved tees la a11 three steen generaters er all of the sleeved teos la i s the generater chosen for the inspeettoa program.

j s whichevet is less. These inspections will include both i the tee and the sleeve.

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4. A tube Laspeettee (pursuant to specifiestaea ,.

l 4.4.6.4.a.8) shall be perfossed es ese selected tube.

If any selected tube does met posatt the passace of the oddy eurtent probe for a tube er sleeve taspection, this shall be tocorded and as adjaeost see shall be I

selected and subjected to a tube taspecties.

i v o H e e,. M " I s.%2 .;:= :t: rAdi-ue= Seet sa as*= = a

! i l~dP*l C,.au,* A 9;,es.itn;;r; of a,,1 --r- e.ti-

'r shalt.imth. tee sT bebbte eet!

,papeeted

, late i prebe duttaga"2I .M&re.,', . sefueling estages.

s. The tubes selected as the seemed and third segles (if requised by Table 4.4-2) during end Lasesvies taspecties any be adjested to a pastial tube *- , : ries psevidens

1. The tubes selected for these semples tastede the tubes from these asses of the tube sheet array ease tubes with imperfeettens were previeue1r sound.

2. The taspeettees Laslude these portions of the tubes )

ease impostostases uses previously feed.

sM( pienestaties

_ .ir;;' ; criteria of the steam generates segelse#jite tute/tde agpost pereest bobbges11 plate Lasposties I I for hot-leg :2: : g;:2 ;_ C i n :-__ r" ' sold-1 (8-- 4 l j

l intersections dous to the 1euset sold-leg tube s pest p to C, J uith issue outside diametes stress ==---*=

Ladientiens. The deteastaaties of 8 tube y- *= tecocci piste m jP intersections having 8080C tadientiene 1, he Desed es the perfosmance of at 1oest a 20 possent reades seg11ag of teos g,,

taspected eyes their fall length. g Th. s.ee n .f e t= ,. sties sm.It b. e1=stit.dsate e .f a., ag.le.p 1 fe11ewaag thase estegories: L_ _

it'4-rAALEY-UNIT 2 3/4410 AMM R W T 50.&};W O

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SURVEILLANCE REQUIREMDITS (Continund) _ .

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4. Fluesine er Rapnir Limit means tho imparfoctisn i i depth at or beyond which the tube shall be repatred 4 l (i.e., sleeved) or removed from service by plugging l

and is greater than or equal to 40% of the naminal

} tube wall thickness. This definition does not apply

! for tubes that meet the F*/L*,, criteria. For a tube l that has been sleeved with a mechanical joint j sleeve, through wall penetration of greater than or l equal to 31% of sleeve nominal wall thickness in i

the sleeve requires the tube to be removed from

s service by plugging. For a tube that has been j

sleeved with a welded joint sleeve, through well penetration greater than or equal to 374 of sleeve nominal wall thickness in the sleeve between the weld joints requires the tube to be removed from service by plugging. This definition does not apply l to tube support plate intersections for which the -

voltsee h-e=' 7 1 ;;;L; criteria are being applied. l 1 Refer to 4.4.4.4.a for the ;12; gg, appliegble to thes intersections.);'n; limit l . Unserviceable describes the condition of a tube or i sleeve it it leaks or contains a defect large l

/6 enough to affect its structural integrity in the event of an operating Basis Earthquake, a loss-of-l coolant accident, or a steam line or feedwater line j break as specatied in 4.4.6.3.c, above.

l S. Tube Inspection means an inspection of the steam j generator tube from the point of entry (hot leg i side) completely around the U-bend to the top j support of the cold leg. For a tube that has been j repaired by sleeving, the tube inspection should include the sleeved portion of the tube.

9. Tube stepair refers to mechanical sleeving, as

described by Westinghouse report WCAF-11178, Rev.

j 1, or laser welded sleeving as described by Westinghouse report echt-13612, which is used to

maintain a tube in service or return a tube to l service. This includes the removal of plugs that j were installed as a corrective or preventive measure.

se La criteria is applicable te eyele 11 only. .

l FARLEY-UNIT 2 3/4 4-12a AMDfDHENT No.11( -

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SURVEILLANCE REQUIRIMDfTS (Cantinued)

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15. Tubi Expensien is that portica of a tube which kno be::a l l increased in diameter by a rolling process such that no l

crevice exists between the outside diameter of the tube l

and the hole in the tubesheet.

Tube support Plate ?i__d ,

Q 'r gg @ 16. t is used for the disoosition oiseteteam generator tube for continued l

service *=e is a m riencingso utside diameter stress '

l g v crosion cracking contines irithin the thickness of the h

._j _ _1_1. _ _ _ 1;;i1 : 21: fn j

I(pidg[ c, j d//At tube i " * ,.support plates.

. ... .' ;, _ i : ni,Q. _t A tube support plate intersections, the repair limit is based on maint mining o ff gegk, steam generator tube serviceability as described below:

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a. MgradationAattributed to outside diameter stress h p- v r) corrosion ' cracking trithin the beusde of the tuba support plate wit bobbin voltage less than er hdHbJ,ed"i M equal t Q2.0 volt will be allowed to remain in l l s.rvicef ,

b. pgradationfattributed to outside diameter stress corrosion c?acking within the bounds of the

[W /0!4 l r J O support plate with bobbia voltage greater .0

- l1 be_renaired or god except as noted (yd2,/f !/ volt @6.4.a.J5tc below.

in 4.4.

} c. J'ndications of potential degradation attributed to

' outside diameter stress corrosion cracking within I C the bounds of the tg suppor1Lplate with a bobbin l 7 voltage greater tha# g.0 voltg7but less than or j

j j

p*' , ,j/M equal teJ.! ;Or may remain in service if a rotating' ;r T l'. Laspection ao.es not estect j

degradation.$ cations of outsi6e diameter

( p0 &* , stress corrosion cracking degradation with a bobbin 1

p voltage greater J ._^ __ will be plugged or (pf fg#

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b repaired.

rT. The' steam generator shall be determined optRABLE after completing the corresponding actions (plug or repair of all tubes exceeding the plugging or repair limit) required by Table

,fer pA 4.4-2.

1. w f [L.44gebiah/yjk w.m MO 3/4 4-13 AMENDMENT NO. 110 FARLEY - UNIT 2 4

r In:ert A

d. If an unscheduled mid-cycle inspection is performed, the following mid-cycle repair limits apply instead of the limits identified in 4.4.6.4.a.16.a, 4.4.6.4.a.16.b, and 4.4.6.4.a.16.c. The mid-cycle repair limits are determined from the following equations:

Vn vmn= 1.0 + NDE + Gr [ CL-At ]

s' CL Van =Vmn- [vun-V n] [ CL-At ]

t CL where:

Vuni. = upper voltage repair limit

, Vuit = lower voltage repair limit Vmn = mid-cycle upper voltage repair limit based on time into cycle l

Van = mid-cycle lower voltage repair limit based

! on Vmn and time into cycle At = length of time since last scheduled inspection during which Vunt. and V tn were implemented .

CL = cycle length (the time between two scheduled steam generator inspections)

Vn = structural limit voltage Gr =

average growth rate per cycle length NDE = 95-percent cumulative probability allowance for nondestructive examination uncertainty (i.e., a value of 20-percent has been approved by NRC)

Implementation of these mid-cycle repair limits should follow the same approach as in TS 4.4.6.(.a.16.a, 4.4.6.4.a.16.b, and 4.4.6.4.a.16.c.

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SURVEILLANCE REQUIRD4ENTS (Cantinued) 4.4.4.5 R ports

a. Following each inservice inspection of steam generator tubes, the number of tubes plugged, repaired or designated F*/L*w in l i each steam generator shall be reported to & Comunission within i 15 days of the completion of the inspection, plugging or repair I effort.

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b. The couplete results of the steam generator tube and sleeve inservice inspection shall be submitted to @ Commission in a 1 Special Report pursuant to Specification 6.9.2 within 12 months l 1 ' following the completion of the inspection. This special l Report shall includes l

} 1. Number and eatent of tubes and sleeves inspected.

} 2. Location and percent of well-thickness penetration for i

each indication of an imperfection.

I 3. Identification of tubes plugged or repaired.

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) c. Results of steam generator tube inspections which fall into Category C-3 shall be considered a REtoftfAS15 EVENT and shall l be reported pursuant to 10CFR50.73 prior to resumption of plant operation. The written report shall provide a description of

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investigations conducted to detershine the cause of the tube i

degradation and corrective measures taken to prevent i recurrence.

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d. For impleneatation of the voltage-based repair criteria to tube j support plate intersections, notify the staff prior to i

returning the steam generator to service Deode 4) should any of j

the following conditions ariset

h. Ifvoltage estimated leakage based on the actual end-of-cyc1h distribution would have exceeded the leak limit 4 (for the postulated main steam line break utilizing licensing basis assumptions) during the previous

( operating cycle.

2. If circumferential crack-like indications are detected at the tube support plate intersections.

3. It indications are identified that entend beyond the oestines of the tube support plate.

f, If the calculated conditional burst probability exceedal

[4. 1 a 10*8, notify the NDC and provide an assessment of the I

[g '"9' safety significance of the occurrence.

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et L* Criteria is applicable to Cycle 11 only.

1. AMENDMENT No.110 TARLEY-UNIT 2 3/4 4-13a

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i If estimated leakage based on the projected end-of-cycle (or if not practical, using the actual measured end-of-cycle) voltage distribution exceeds the leak limit j

i (determined from the licensing basis dose calculation for the postulated main steam line break) for the next operating

{ cycle.

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4. If indications are identified at the tube support plate i

elevations that are attributable to primary water stress 4

corrosion cracking.

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5. If the calculated conditic..al burst probability based on the i projected end-of-cycle (or if not practical, using the i

actual , measured end-of-cycle) voltage distribution exceeds i 1 x 10, notify the NRC and provide an assessment of the safety significance of the occurrence.

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l 3/4.4 6 STEAM gds 1AATOR_S

- N Surve111ance Aspirements for taspecties of the steam generator teos s i

ensure that the structural integrity of this portica of the RCS will be antatataed. The program for Laservice inspeetten of steam generator teos i to based on a sedification of Regulatory outdo 1.83, movistes 1. !aservise j

Inspeetten of steam generator testag is essential La order to maintata e surveillanee of the condittens ein the tubes La the event that there is evidence of aseheatsal damage er progressive degradation due to design, asaufactustag errors, or inservice esadittees that lead to correstes.

faservice insposties of steam generator tubing also provides a means of characteristag the satste and eause of any tube dogsadaties se that j eerrestive measures eam be taken.

J The plaat is esposted to be operated La manner seek that the secondary eeelaat will be maintalmed withis these ebentetsy 11mits found to result la negligible eerrestem of the steam generates tubes. If the seenadary I eselaat ebenistry is set malatained withis these 11atte, leealised 1 corressoa any likely result is stress correstes eraching. The essent of cracking during plant operaties would be 11atted by the 11attaties of steam.

generates tube leakage between the prianay ecolant system and the seemedasy l coolant system (primary-to-seemedney leakage = 1Sg gallons per day pee steam generateel. Cracks havtag a primary-to-seeeadary leakage less thea

. this 11att Asstag sposaties will have as adequate margia of safety to withstand the leads 1syssed daring neomal operaties and by postulated aseidents. Operational leakage of this magmatude ena he readily detected by estating Farley Wait 2 radiatica maalters. Leakage la eseess of $1s

( limit will require plant shutdoom and an unseheduled inspecties, during i

uhich the leaking teos will be loested and plugged og sepaired.

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The repair 11att fos cated at tee support plate intersections is based an i the analysis ==*a8==d La WCnp-tasti, Revistem 3, 4. N. yarley Smits 1 and l q

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2 86 Tube riegging Cetteria fos 900cc at Tee Stepert plates,' and e

M g f doetmentaties contained in EPRI Seport TR-1964g1, Revistoa 1, *fWR steam i

M Generator Tube Repair Liatts - Technical Support Doetment fos Outside l cf) w Diameter Stress Corsestem Caseking et Tube Support plates.* The i

j applicaties of this eriteria is based em liatting primary-to-seeeedary  !

leaka 3

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Qr. a.ge t .a during d.d. a steen line break to ensuse the applicab wastage-type defects are unlikely with propes ehemistry treatment of the seceedssy eselaat. Bewever, even if a detest should develop la servies, it

! will be found daring sabeduled Laservien steam peassager tee esaminations.

{ Pluggiaq er repair v111 he required for all tubes with imperfections escoeding 40% of the tube nominal watt thickness. If a sleeved tube is i

1 found to have threefh wall penetratten of greater than es equal to all for the asshanical sleeve and 37% for the it must be laser welded plugged. The sleeve all and of 314sleeve timitsseminal well thickness la the sleeva, are derived free R. 4.1.121 calculattens with 20% added for senservatism. j The portion of the tube and the sleeve for which indiestions of well degradation must be evaluated saa be summarised as fe118was 8 3/4 4-3 AMENEpWT NO. W FAALEY-UNIT 2 q

Mhb &)Vo e

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The voltage-based' repair limits of 4.4.6.4.a.16 implement the guidance in GL )

95-05 and are applicable only to Westinghouse-designed steam generators (SGs)  !

with outside diameter stress corrosion cracking (ODSCC) located at the tube-to-tube support plate intersections. The voltage-based repair limits are not applicable to other forms of SG tube degradation nor are they applicable to ODSCC that occurs at other locations within the SG. Additionally, the repair I criteria apply only to indications where the degradation mechanism is  :

dominantly axial ODSCC with no significant cracks extending outside the l

,y thickness of.the support plate. Refer to GL 95-05 for additional description i of the degradation morphology.

Implementation of 4.4.6.4.a.16 requires a derivation of the voltage structural limit from the burst versus voltage empirical correlation and then the 1 subsequent derivation of tne voltage repair limit from the structural limit (which is then implemented by this surveillance).

The voltage structural limit is the voltage from the burst pressure / bobbin voltage correlation, at the 95-percent prediction interval curve reduced to account for the lower 95/95-percent tolerance bound for tubing material properties et 650 *F (i.e., the 95-percent LTL curve). The voltage structural limit must be adjusted downward to account for potential flaw growth during an operating interval and to account for NDE uncertainty. The upper voltage  !

repair limit; Vun , is determined from the structural voltage limit by applying the following equation:

Vun = Vn - Vcc - Vux where Va, represents the allowance for flaw growth between inspections and Vux represents the allowance for potential sources of error in the measurement of the bobbin coil voltage. Further discussion of the assumptions necessary to determine the voltage repair limit are discussed in GL 95-05.

The mid-cycle equation in 4.4.6.4.a.16.d should only be used during unplanned inspections in which eddy current data is acquired for indications at the tube support plates.

4.4.6.5 implements several reporting requirements recommended by GL 95-05 for situations which the NRC wants to be notified prior to returning the SGs to service. For the purposes of this reporting requirement, leakage and conditional burst probability can be calculated based on the as-found voltage distribution rather than the projected end-of-cycle voltage distribution  !

(refer to GL 95-05 for more information) when it is not practical to complete i these calculations using the projected EOC voltage distributions prior to returning the SGs to service. Note that if leakage and conditional burst probability were calculated using the measured EOC voltage distribution for the purposes of addressing the GL section 6.a.1 and 6.a.3 reporting criteria, I then the results of the projected EOC voltage distribution should be provided per the GL section 6.b(c) criteria.

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Unit 2 Technical Specification Pages Replacement Pages for Voltage-Based Repair Criteria l

Page 3/4 4-10 Replace Page 3/4 4-12a Replace Page 3/4 4-13 Replace Page 3/4 4-13a Replace l Page 3/4 4-13b Insert

! Page B 3/4 4-3 Replace Page B 3/4 4-3a Replace-Page B 3/4 4-3b Replace Page B 3/4 4-3c Insert l

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REACTOR COOLANT SYSTEM I

SURVEILLANCE REQUIREMENTS (Continued) i 2. Tubes in those areas where experience has indicated l potential problems.

3. At least 3% of the total number of sleeved tubes in all three steam generators or all of the sleeved tubes in the generator chosen for the inspection program, whichever is less. These inspections will include both the tube and the s sleeve.

l 4. A tube inspection (pursuant to Specification 4.4.6.4.a.8) shall be performed on each selected tube. If any selected tube does not permit the passage of the eddy current probe for a tube or sleeve inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.

5. Indications left in service as a result of application of l the tube support plate voltage-based repair criteria shall be inspected by bobbin coil probe during all future 1 refueling outages.

c. The tubes selected as the second and third samples (if required by Table 4.4-2) during each inservice inspection may be subjected to a partial tube inspection provided:

1. The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found.

2. The inspections include those portions of the tubes where imperfections were previously found.

d. Implementation of the steam generator tube / tube support plate repair criteria requires a 100 percent bobbin coil inspection for hot-leg and cold-leg tube support plate intersections down to the lowest cold-leg tube support plate with known outside diameter stress corrosion cracking (ODSCC) indications. The determination i of the lowest cold-leg tube support plate intersections having l ODSCC indications shall be based on the performance of at least a 20 percent random sampling of tubes inspected over their full i length.  !

The results of each sample inspection shall be classified into one of the ,

following three categories: i EARLEY-UNIT 2 3/4 4-10 AMENDMENT NO.

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) _,

6. Plugging or Repair Limit means the imperfection depth at or beyond which the tube shall be repaired (i.e., sleeved) or  ;

removed from service by plugging and is greater than or  ;

equal to 40% of the nominal tube wall thickness. This i definition does not apply for tubes that meet the F*/L*,,

criteria. For a tube that has been sleeved with a mechanical joint sleeve, through wall penetration of greater I

%> than or equal to 31% of sleeve nominal wall thickness in the sleeve requires the tube to be removed from service by plugging. For a tube that has been sleeved with a welded joint sleeve, through wall penetration greater than or equal f to 37% of sleeve nominal wall thickness in the sleeve ,

between the weld joints requires the tube to be removed from  !

I service by plugging. This definition does not apply to tube support plate intersections for which the voltage-based l repair criteria are being applied. Refer to 4.4.6.4.a.16 )

for the repair limit applicable to these intersections.  !

7. Unserviceable describes the condition of a tube or sleeve if I 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 j feedwater line break as specified in 4.4.6.3.c, above. l

8. Tube Inspection means an inspection of the steam generator i tube from the point of entry (het leg side) completely I around the U-bend to the top support of the cold leg. For a tube that has been repaired by sleeving, the tube inspection should include the sleeved portion of the tube. )

9. Tube Repair refers to mechanical sleeving, as described by Westinghouse report WCAP-11178, Rev. 1, or laser welded sleeving as described by Westinghouse report WCAP-12672, which is used to maintain a tube in service or return a tube to service. This includes the removal of plugs that were installed as a corrective or preventive measure.

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1. 1. L* Criteria is applicable to Cycle 11 only.

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! FARLEY-UNIT 2 3/4 4-12a AMENDMENT NO.

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• l REACTOR COOLANT SYSTEM '

SURVEILLANCE REQUIREMENTS (Continued)

, 15. Tube Expansion is that portion of a tube which has been l

increased in diameter by a rolling process such that no .

crevice exists between the outside diameter of the tube and I l the hole in the tubesheet.

16. Tube Support Plate Repair Limit is used for the disposition of an alloy 600 steam generator tube for continued service that is experiencing predominately axially oriented outside s diameter stress corrosion cracking confined within the l thickness of the tube support plates. At tube support plate l intersections, the repair limit is based on maintaining steam generator tube serviceability as described below:

a.

Steamgeneratortubes,whosedegradationisattributedl to outside diameter stress corrosion cracking within the bounds of the tube support plate with bobbin voltages less than or equal to the lower voltage 1 1

repair limit (2.0 volts], will be allowed to remain in  !

service. I l

b. Steam generator tubes, whose degradation is attributed l to outside diameter stress corrosion cracking within j the bounds of the tube support plate with a bobbin I voltage greater than the lower voltage repair limit (2.0 volts], will be repaired or plugged except as noted in 4.4.6.4.a.16.c below.

c. Steam generator tubes, with indications of potential degradation attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with a bobbin voltage greater than the lower voltage repair limit (2.0 volts] but less than or equal to the upper voltage repair limit *, may remain in service if a rotating probe inspection does not detect degradation. Steam generator tubes, with indications of outside diameter stress corrosion cracking degradation with a bobbin voltage greater than the upper voltage repair limit *, will be plugged l ,

or repaired.

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The upper voltage repair limit is calculated according to the methodology in Generic Letter 95-05 as supplemented.

EARLEY-UNIT 2 3/4 4-13 AMENDMENT NO.

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

d. If an unscheduled mid-cycle inspection is performed, I i

the following mid-cycle repair limits apply instead of '

the limits identified in 4.4.6.4.a.16.a, 4.4.6.4.a.16.b, and 4.4.6.4.a.16.c. The mid-cycle repair limits are determined from the following equations:

I YSt Vma t= 1.0 + NDE + Gr ( CL-At )  !

CL YMLRL= Vat;at-(Vunt-V t at) ( CL-At )

CL where: l V.;,t =

upper voltage repair limit  :

Vt ,t =

lower voltage repair limit  !

=

Vmat mid-cycle upper voltage repair limit based on time into cycle Vm.,t =

mid-cycle lower voltage repair limit based on Vmat and time into cycle at = length of time,since last scheduled I inspection during which Vunt and Vat t were implemented CL = cycle length (the time between two scheduled steam generator inspections)

=

Vst structural limit voltage Gr =

average growth rate per cycle length NDE =

95-percent cumulative probability allowance for nondestructive examination uncertainty (i.e., a value of 20 percent has been approved by NRC)

Implementation of these mid-cycle repair limits should follow the same approach as in TS 4.4.6.4.a.16.a, 4.4.6.4.a.16.b, and 4.4.6.4.a.16.c.

b. The steam generator shall be determined OPERAB71 after completing the corresponding actions (plug or repair of al.' cubes exceeding the plugging or repair limit) required by T3ble 4.4-2.

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FARLEY-UNIT 2 3/4 4-13a AMENDMENT NO.

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.6.5 Reports

a. Following each inservice inspection of steam generator tubes, the number of tubes plugged, repaired or designated F*/L*., in each steam generator shall be reported to the Commission within 15 days of the completion of the inspection, plugging or repair effort,

b. The complete results of the steam generator tube and sleeve inservice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection. This Special Report shall include:

1. Number and extent of tubes and sleeves inspected.

2. Location and percent of wall-thickness penetration for each indication of an imperfection.

3. Identification of tubes plugged or repaired.

c. Results of steam generator tube inspections which fall into Category C-3 shall be considered a REPORTABLE EVENT and shall be reported pursuant to 10CFR50.73 prior'to resumption of plant operation. The written report shall provide a description of investigations conducted to determine the cause of the tube degradation and corrective measures taken to prevent recurrence.

d. For implementation of the voltage-based repair criteria to tube support plate intersections, notify the staff prior to returning the steam generator to service (Mode 4) should any of the following conditions arise:

1. If estimated leakage based on the projected end-of-cycle (or if not practical, using the actual measured end-of-cycle) voltage distribution exceeds the leak limit (determined from the licensing basis dose calculation for the postulated main steam line break) for th'e next operating cycle.

2. If circumferential crack-like indications are detected at the tube support plate intersections.

3. If indications are identified that extend beyond the confines of the tube support plate.

4. If indications are identified at the tube support plate elevations that are attributable to primary water stress corrosion cracking.

5. If the calculated conditional burst probability based on the projected end-of-cycle (or if not practical, using the actual measured end-of-cycle) voltage distribution exceeds 1 x 10-2, notify the NRC and provide an assessment of the safety significance of the occurrence.

1. 1. L* Criteria is applicable to Cycle 11 only.

FARLEY-UNIT 2 3/4 4-13b AMENDMENT NO.

REACTOR COOLANT SYSTEM 4 BASES

! 3/4.4.6 STEAM GENERATORS 4

4 4

The Surveillance nequirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be maintained. The program for inservice inspection of steam generator tubes is s based on a modification of Regulatory Guide 1.83, Revision 1. Inservice s inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due to design, i manufacturing errors, or inservice conditions that lead to corrosion.

Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective l measures can be taken.

{ The plant is expected to be operated in a manner such that the secondary

coolant will be maintained within those chemistry limits found to result in negligible corrosion of the steam generator tubes. If the secondary coolant chemistry is not maintained within these limits, localized corrosion may likely result in stress corrosion cracking. The extent of cracking during 5

plant operation would be limited by the limitation of steam generator tube

leakage between the primary coolant system and the secondary coolant system l

(primary-to-secondary leakage = 150 gallons per day per steam generator).

Cracks having a primary-to-secondary leakage less than this limit during

operation will have an adequate margin of safety to withstand the loads 4 imposed during normal operation and by postulated accidents. Operational leakage of this magnitude can be readily detected by existing Farley Unit 2  ;

radiation monitors. Leakage in excess of this limit will require plant I i l shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugged or repaired. 1

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The voltage-based repair limits of 4.4.6.4.a.16 implement the guidance in GL l d

95-05 and are applicable only to Westinghouse-designed steam generators (SGs)  !

with outside diameter stress corrosion cracking (CDSCC) located at the tube-to-tube support plate intersections. The voltage-based repair limits are not

,~

applicable to other forms of SG tube degradation nor are they applicable to OD3CC that occurs at other locations within the SG. Additionally, the repair

criteria apply only'to indications where the degradation mechanism is dominantly axial CDSCC with no significant cracks extending outside the thickness of the support plate. Refer to GL 95-05 for additional description l of the degradation morphology.

Implementation of 4.4.6.4.a.16 requires a derivation of the voltage structural limit from the burst versus voltage empirical correlation and then the ,

subsequent derivation of the voltage repair limit from the structural lindt  !

(which is then implemented by this surveillance).

EARLEY-UNIT 2 B 3/4 4-3 AMENDMENT NO.

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REACTOR COOLANT SYSTEM EASES i

! The voltage structural limit is the voltage from the burst pressure / bobbin l voltage correlation, at the 95-percent prediction interval curve reduced to l account for the lower 95/95-percent tolerance bound for tubing material l properties at 650 'F (i.e., the 95-percent LTL curve). The voltage structural i limit must be adjusted downward to account for potential flaw growth during an i operating interval and to account for NDE uncertainty. The upper voltage l repair limit; Ven , it determined from the structural voltage limit by applying l

the following equation:

U vgu =Vn-v,-vec s  !

where Vs, represents the allowance for flaw growth between inspections and v ec represents the allowance for potential sources of error in the measurement of 1 the bobbin coil voltage. Further discussion of the assumptions necessary to l determine the voltage repair limit are discussed in GL 95-05. '

The mid-cycle equation in 4.4.6.4.a.16.d should only be used during unplanned l inspections in which eddy current data is acquired.for indications at the tube j support plates.

I 4.4.6.5 implements several reporting requirements recommended by GL 95-05 for l situations which the NRC wants to be notified prior to returning the SGs to I service. For the purposes of this reporting requirement, leakage and conditional burst probability can be calculated based on the as-found voltage distribution rather than the projected end-of-cycle voltage distribution (refer to GL 95-05 for more information) when it is not practical to complete these calculations using the projected EOC voltage distributions prior to returning the SGs to service. Note that if leakage and conditional burst probability were calculated using the measured EOC voltage distribution for the purposes of addressing the GL section 6.a.1 and 6.a.3 reporting criteria, then the results of the projected EOC voltage distribution should be provided l per the GL section 6.b(c) criteria.

i Wastage-type defects are unlikely with proper chemistry treatment of the J secondary coolant. However, even if a defect should develop in service, it i will be found during scheduled inservice steam generator tube exandnations.

Plugging or repair will be required for all tubes with imperfections exceeding 40% of the tube nominal wall thickness. If a sleeved tube is found to have through wall penetration of greater than or equal to 31% for the mechanical j sleeve and 37% for the laser welded sleeve of sleeve nominal wall thickness in the sleeve, it must be plugged. The 31% and 37% limits are derived from R. G.

1.121 calculations with 20% added for conservatism. The portion of the tube and the sleeve for which indications of wall degradation must be evaluated can j be summarized as follows:

a. Mechar.ical

1. Indications of degradation in the entire length of the sleeve must be evaluated against the sleeve plugging limit.

2. Indication of tube degradation of any type including a complete guillotine break in the tube between the bottom of the upper joint

( and the top of the lower roll expansion does not require that the

tube be removed from service.

FARLEY-UNIT 2 B 3/4 4-3a AMENDMENT NO.

l REACTOR COOLANT SYSTEM BASES

3. The tube plugging limit continues to apply to the portion of the tube in the entire upper joint region and in the lower roll expansion. As noted above, the sleeve plugging limit applies to ,

these areas also. '

4. The tube plugging limit continues to apply to that portion of the

%> tube above the top of the upper joint. i

b. Laser Welded

1. Indications of degradation in the length of the sleeve between the  ;

weld joints must be evaluated against the sleeve plugging limit. l i

2. Indication of tube degradation of any type including a complete break in the tube between the upper weld joint and the lower weld l

joint does not require that the tube be removed from service.  !

3. At the weld joint, degradation must be evaluated in both the sleeve and tube.

4. In a joint with more than one weld, the weld closest to the end of l

the sleeve represents the joint to be inspected and the limit of j the sleeve inspection.  !

I

5. The tube plugging limit continues to apply to the portion of the {

tube above the upper weld joint and below the lower weld joint. ]

F* tubes do not have to be plugged or repaired provided the remainder of the tube within the tubesheet that is above the F* distance is not degraded. The F* distance-is equal to 1.79 inches and is measured down from the top of the tubesheet or the bottom of the roll transition, whichever is lower in elevation. Included in this distance is an allowance of 0.25 inch for eddy current elevation measurement uncertainty.

L* is similar to F*; however, bands of axial degradation are allowed as long as sufficient non-degraded tubing is available to ensure structural and leakage integrity. L* criterion is only applicable for Unit 2 Cycle 11. l Provided below is the Unit 2 Cycle 11 specific L* criterion: l FARLEY-UNIT 2 B 3/4 4-3b AMENDMENT NO. l

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l REACTOR COOLANT SYSTEM BASES l

l Unit 2 Cycle 11 Specific L* Criterion Parameter Value Minimum distance of SRE 2.07 inches Maximum number of distinct degradation areas in a 5 ,

band 1 Maximum inclination angle within a single band 15 degrees U Maximum crack length .39 inches Minimum distance of SRE from the bottom of the 1.45 inches transition roll to the top of the indication j

Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect wastage type degradation that has penetrated 20%

of the original tube wall thickness.

Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be reported to the Commission pursuant to 10 CFR 50.73 prior to resumption of plant operation. Such cases will be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, tests, additional eddy-l current inspection, and revision to the Technical Specifications, if necessary.

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l FARLEY-UNIT 2 B 3/4 4-3c AMENDMENT NO. l l

Attachment 2 Unit 2 Technical Specification Pages for F* Repair Criteria l

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

10. Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to service to establish a baseline condition of the tubing. This inspection shall be performed after the field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.

. INSERT A

11. F' Dict:nc: i: th: di: ten : cf th: :np:nded p::tien f : tub: which s' provid:: : cufficient length of und:g :d:d tub: capancien :: :::ict i pulleut of th tub: f::: the tub::h:::. The F' distan : i equ:1 to j 1.70 in h:: and i: m ::ured d un f :: the t:p of th tub :h::t : th:

b;tter :f th ::11 t nciti:n, which:v : i lex:: ir ci v:ti n 4

12. F* Tube is a tube:

a) with degradation equal to or greater than 40% below the F* distance, and b) which has no indication of imperfections greater than or equal to 20% of nominal wall thickness within the F* distance, and c) that remains inservice.

If the above criteria cannot be met, then the L* tube criteria may be applied or the tube must be plugged or repaired.

13. L* Lengthn is the length of the expanded portion of the tube into the tube sheet from the bottom of the rolled transition or the top of the tube sheet, which ever is lower, that has been determined to be 1.45 inches.

14. L* Tube n: a) is a tube with degradation equal or greater than 40%

below the L* 1ength and not degraded within the L* length; b) the eddy current indication of degradation below the L* 1ength must be determined to be the result of cracks with an orientation no greater than 15 degrees from axial; c) the L* criteria shall be limited to a maximum of 600 tube ends per steam generator; d) tubes qualifying as F* tubes are not classified as L* tubes; e) a minimum of 3.1 inches of the tube into the tubesheet from the top of tubesheet or bottom of the rolled transition, which ever is lower, shall be inspected using rotating pancake coil eddy current technique or an inspection method shown to give equivalent or better information on the orientation and length of axial cracks; f) a minimum aggregate of 2.07 inches of sound roll expansions g) a maximum crack length of .39 inches; h) a maximum of 5 distinct indications with a single band of tube degradation; ar.i il that remains in service.

1. 1. L* Criteria is applicable to Cycle 11 only. l FARLEY-UNIT 2 3/4 4-12b AMENDMENT NO.

. . . - _ . . . . ~ . _ _ - ._..____.___-_.__._._._____-._-._..-....__.m_.._. _

a 1

i Insert A

)

l 11. F* Distance is the distance of the expanded portion of a tube which provides a sufficient length of undegraded tube expansion to resist pullout of the tube from the tubesheet. The F* distance is equal to 1.54 inches plus ,

! allowance'for eddy current uncertainty measurement and is measured down from the top of the tube sheet or the bottom of the roll transition, whichever is

, lower in elevation. The allowance for eddy current uncertainty is documented

}

in the steam generator eddy current inspection procedure.

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REACTOR COOLANT SYSTEM BASES

3. The tube plugging limit continues to apply to the portion of the tube in the entire upper joint region and in the lower roll expansion. As noted above, the sleeve plugging limit applies to these areas also.

4. The tube plugging limit continues to apply to that portion of the C tube above the top of the upper joint.

b. Laser Welded

1. Indications of degradotion in the length of the sleeve between the weld joints must be evaluated against the sleeve plugging limit. l l

2. Indication of tube degradation of any type including a complete break in the tube between the upper weld joint and the lower weld f joint does not require that the tube be removed from service.

3. At the weld joint, degradation must be evaluated in both the sleeve and tube. j

4. In a joint with more than one weld, the weld closest to the end of the sleeve represents the joint to be inspected and the limit of the sleeve inspection.

5. The tube plugging limit continues to apply to the portion of the tube above the upper weld joint and below the lower weld joint.  ;

F* tubes do not have to be plugged or repaired provided the remainder of the tube within the tubesheet that is above the F* distance is not degraded. The F* distance is equal to 1.54 inches plus allowance for eddy current uncertainty measuremment 1.70 inche: and is measured down from the top of the tubesheet or the bottom of the roll transition, whichever is lower in  ;

elevation. Included ir thi: dict:n : i: :n :ller:n;; cf 0.25 inch for cddy current ci c:ti:n ::::ur . nt un:::tcinty.

i L* is similar to F*; however, bands of axial degradation are allowed as long ,

as sufficient non-degraded tubing is available to ensure structural and I leakage integrity. L* criterion is only applicable for Unit 2 Cycle 11. 1 Provided below is the Unit 2 Cycle 11 specific L* criterion:

I I

e FARLEY-UNIT 2 B 3/4 4-3b AMENDMENT NO. l

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Unit 2 Technical Specification Pages Replacement Pages for F* Repair Criteria l l

Page 3/4 4-12b Replace Page B 3/4 4-3a Replace l

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

10. Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to service to establish a baseline condition of the tubing. This l inspection shall be performed after the field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.

11. F* Distance is the distance of the expanded portion of a tube which d' provides a sufficient length of undegraded tube expansion to resist pullout of the tube from the tubesheet. The F* distance is equal to 1.54 inches plus allowance for eddy current uncertainty measurement and is measured down from the top of the tube sheet or the bottom of the

! roll transition, whichever is lower in elevation. The allowance for l

eddy current uncertainty is documented in the steam generator eddy current inspection procedure.

12. F* Tube is a tube:

a) with degradation equal to or greater than 40% below the F* distance, and b) which has no indication of imperfections greater than or equal to 20% of nominal wall thickness within the F* distance, and c) that remains inservice.

If the above criteria cannot be met, then the L* tube criteria may be applied or the tube must be plugged or repaired.

13. L* Lengthu is the length of the expanded portion of the tube into the tube sheet from the bottom of the rolled transition or the top of the tube sheet, which ever is lower, that has been determined to be 1.45 inches.

14. L* Tube n: a) is a tube with degradation equal or greater than 40%

l below the L* length and not degraded within the L* length; b) the eddy '

current indication of degradation below the L* length must be determined to be the result of cracks with an orientation no greater than 15 degrees from axial; c) the L* criteria shall be limited to a maximum of 600 tube ends per steam generators d) tubes qualifying as F* tubes are I not classified as L* tubes; e) a minimum of.3.1 inches of the tube into the tubesheet from the top of tubesheet or bottom of the rolled transition, which ever is lower, shall be inspected using rotating pancake coil eddy current technique or an inspection method shown to give equivalent or better information on the orientation and length of axial cracks; f) a minimum aggregate of 2.07 inches of sound roll expansion; g) a maximum crack length of .39 inches; h) a maximum of 5 l distinct indications with a single band of tube degradation; and 1) that I

remains in service.

I i ## L* Criteria is applicable to Cycle 11 only.

t FARLEY-UNIT 2 3/4 4-12b AMENDMENT NO.

REACTOR COOLANT SYSTEM BASES

3. The tube plugging limit continues to apply to the portion of the tube in the entire upper joint region and in the lower roll expansion. As noted above, the sleeve plugging limit applies to these areas also.

4. The tube plugging limit continues to apply to that portion of the tube above the top of the upper joint.

s'

b. Laser Welded

1. Indications of degradation in the length of the sleeve between the weld joints must be evaluated against the sleeve plugging limit.

2. Indication of tube degradation of any type including a complete break in the tube between the upper weld joint and the lower weld joint does not require that the tube be. removed from service.

3. At the weld joint, degradation must be evaluated in both the sleeve and tube.

4. In a joint with more than one weld, the weld closest to the end of the sleeve represents the joint to be inspected and the limit of the sleeve inspection.

5. The tube plugging limit continues to apply to the portion of tha tube above the upper weld joint and below the lower weld joint.

F* tubes do not have to be plugged or repaired provided the remainder of the tube within the tubesheet that is above the F* distance is not degraded. The F* distance is equal to 1.54 inches plus allowance for eddy current uncertainty measurement and is measured down from the top of the tubesheet or the bottom of the roll transition, whichever is lower in elevation.

I L* is similar to F*; however, bands of axial degradation are allowed as long i as sufficient non-degraded tubing is available to ensure structural and leakage integrity. L* criterion is only applicable for Unit 2 Cycle 11.  ;

Provided below is the Unit 2 Cycle 11 specific L* criterion: '

FARLEY-UNIT 2 B 3/4 4-3b AMENDMENT NO.

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Attachment 3 Unit 2 Technical Specification Pages for L* Repair Criteria l and Deletion of Cycle-Specific L*

e Unit 2 Technical Specification Page Markups for L* Repair Criteria and Deletion of Cycle-Specific L*

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REACTOR COOLANT SYSTEM 3/4.4.6 STEAM GENERATOR.}

LIMITING CONDITION FOR OPERATION 3.4.6 Each steam generator shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one or more steam generators inoperable, restore the inoperable s' generator (s) to OPERABLE status prior to increasing Tavg above 200*F.

l SURVEILLANCE REQUIREMENTS 4.4.6.0 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.

4.4.6.1 Steam Generator Sample Selection and Inspection - Each steam generator shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 4.4-1.

4.4.6.2.1 Steam Generator Tube # Sample Selection and Inspection - The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.4-2. The inservice inspection of steam generator tubes shall be performed at the frqquencies specified in Specification 4.4.6.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.6.4.

The tubes selected for each inservice inspection shall include at least 3% of l the total number of tubes in all steam generators. Selection of tubes to be '

inspected is not af fected by the F*/L* designation. When applying the l exceptions of 4.4.6.2.1.a through 4.4.6.2.1.c, previous defects or l imperfections in the area repaired by sleeving are not considered an area l requiring re-inspection. The tubes selected for these inspections shall be '

selected on a random basis except: 1

a. Where experience in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50s of the tubes inspected shall be from'these critical areas.

b. The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of,each steam generator l

shall include: '

1. All nonplugged tubes that previously had detectable wall penetrations greater than 20%.

1. When referring to a steam generator tube, the sleeve shall be considered a part of the tube if the tube has been repaired per Specification 4.4.6.4.a.9. i

"" L' criteri: i: applicable te Cy:1 11 :.nly. l l

FARLEY-UNIT 2 3/4 4-9 AMENDMENT NO.

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e REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

Category Inspection Results C-1 Less than 5% of the total tubes inspected are degraded j tubes and none of the inspected tubes are defective.

)

C-2 One or more tubes, but not more than 14 of the total tubes

{

inspected are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.

C-3 More than 10% of the total tubes inspected are degraded 1 tubes or more than 1% of the inspected tubes are defective. I s

' I Note: In all inspections, previously degraded tubes or sleeves must exhibit significant (greater than 10%) further wall penetrations to be included in the above percentage calculations.

4.4.6.2.2 Steam Generator F*/Lt Tube Inspection - In addition to the l minimum sample size as determined by Specification 4.4.6.2.1, all F*/L* tubes will be inspected within the tubesheet region. The results of this inspection will not be a cause for additional inspections per Table 4.4-2.

4.4.6.3 Inspection Frequencies - The above required inservice inspections of steam generator tubes shall be performed at the following frequencies:

a. The first inservice inspection shall be performed after 6 Effective Full Power Months but within 24 calendar months of initial criticality. Subsequent inservice inspections shall be

)

performed at intervals of not less than 12 nor more than 24 l calendar months after the previous inspection. If two consecutive l inspections following service under AVT conditions, not including l the preservice inspection, result in all inspection results falling into the C-1 category or if two consecutive inspections j

demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months.

j

b. If the results of the inservice inspection of a steam generator conducted in accordance with Table 4.4-2 at 40 month intervals fall in Category C-3, the inspection frequency shall be increased to at least once per 20 months. The increase in inspection frequency shall apply until the subsequent inspections satisfy the

criteria of Specification 4.4.6.3.a; the interval may then be extended to a maximum of once per 40 months.

c. Additional, unscheduled inservice inspections shall be performed

' on each steam generator in accordance with the first sample inspection specified in Table 4.4-2 during the shutdown subsequent l to any of the following conditions

1. 1. L' Criteri: i: Opplicable t: Cycle 11 cr.ly. l

, FARL"Y-UNIT 2 3/4 4-11 AMENDMENT NO.

s REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

6. Pluqqing or Repair Limit means the imperfection depth at or beyond which the tube shall be repaired (i.e., sleeved) or removed from service by plugging and is greater than or equal to 40% of the nominal tube wall thickness. This definition does not apply for tubes that meet the F*/L*.,

criteria. For a tube that has been sleeved with a mechanical joint sleeve, through wall penetration of greater U than or equal to 31% of sleeve nominal wall thickness in the sleeve requires the tube to be removed from service by plugging. For a tube that has been sleeved with a welded joint sleeve, through wall penetration greater than or equal to 37% of sleeve nominal wall thickness in the sleeve between the weld joints requires the tube to be removed from service by plugging. This definition does not apply to tube support plate intersections for which the voltage-based repair criteria are being applied. Refer to 4.4.6.4.a.16 l for the repair limit applicable to these intersections.

7. Unserviceable describes the condition of a tube or sleeve 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 4.4.6.3.c, above.

8. Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg. For a tube that has been repaired by sleeving, the tube inspection should include the sleeved portion of the tube.

9. Tube Repair refers to mechanical sleeving, as described by Westinghouse report WCAP-11178, Rev. 1, or laser welded sleeving as described by Westinghouse report WCAP-12672, which is used to maintain a tube in service or return a tube to service. This includes the removal of plugs that were installed as a corrective or preventive measure.

1. " L' Criteri i: pplicabi; to Cycle 11 :nly.

FARLEY-UNIT 2 3/4 4-12a AMENDMENT NO.

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

10. Preservice Inspection means an inspection of the full length of each l tube in each steam generator performed by eddy current techniques prior i

to service to establish a baseline condition of the tubing. This inspection shall be performed after the field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected  ;

to be used during subsequent inservice inspections.  ;

11. F* Distance is the distance of the expanded portion of a tube which 4 e provides a sufficient length of undegraded tube expansion to resist  !

pullout of the tube from the tubesheet. The F* distance is equal to l 1.54 inches plus allowance for eddy current uncertainty measurement and is measured down from the top of the tube sheet or the bottom of the  :

roll transition, whichever is lower in elevation. The allowance for l

eddy current uncertainty is documented in the steam generator eddy current inspection procedure.

12. F* Tube is a tube:

a) with degradation equal to or greater than 40% below the F* distance, and b) which has no indication of imperfections greater than or equal to 20% of nominal wall thickness within the F* distance, and c) that remains inservice.

If the above criteria cannot be met, then the L* tube criteria may be applied or the tube must be plugged or repaired.

Znsert A

13. L' Lengthu i: the length of th: expanded p;: tion of the tube int: the tub: :h::t f:: the better ;f th: ::lled t nciti n :: the top of the I

.._.u_ .u.

. __. .., .u... u. . . . . _ _ _ . - , ..

. . . . . u. .. u. . .__u._._._.

___:__2

. . . . ~ . . . ._u_.. ~~ ,. . ~ ,e i nch :: .

11 L' Tub u: :) i: ; tub; witt deg :detion equal :: g : te than 105

v. ,___

be., _ . . . u.. . ._ ....,.e ......2___.2._,2

.. __; __. --,... ..:.u..._. .t.._..,___u..,.

ui

-, .. . u. ._ . 2 2 .,.

current indic: tier of d:g::d:ti:n b ler the L' length mu:t be determin d to be th: ::: ult of ::::k: .ith :n ::icntation n g ::te: th:n 15 deg; :: f::: nicl; c) th: L' crite:i 0h:11 50 limit d t: monimur of 500 tub :nd: p:: :te:r gent::ter; di tub:: qu:lifying :: T' t abee-eee nt ci;;;ifi d :: L' tub;;; ;; ; minimur Of 3.1 inch : Of th tub: in;;

Un: tub::h::t f:;r th: top of tube:h::t :: better of th: : lled I trancition, which :v:: i: 10u::, ch:11 be in:p :::d u:ing : tsting I panech ::i1 cddy current ::chnique :: en in:p::ticr :th:d :houn te giv equivalent :: bett:: information :n th: ::icatation and length cf nial :::ch:; fl : minimur ;gg : gat; cf 2.07 inch;; cf : und 2:11 enpan icr; g; : ::nimur :::ch 1:ngth cf .30 inch::; ' m nimur f 5 distinct indication: with : : ingle band f tub d:g;;d: tion; and u that

i n: i r :::vi::.

"" L' Criteri i: applicable to Cycle 11 only.

I FARLEY-UNIT 2 3/4 4-12b AMENDMENT NO.

1 Ins rt A

13. L* Length is the length of the expanded portion of the tube into the tube sheet from the bottom of the rolled transition or the top of the tube sheet, which ever is lower, that has been determined to be .5 inches plus allowance for eddy current measurement uncertainty. The allowance for eddy current' uncertainty is documented in the steam generator eddy current inspection procedure.

s 14. L* Tuber a) is a tube having degradation equal or greater than 40% through wall that is below the L* 1ength-and not degraded within the L* 1ength; b) the eddy current indication of degradation below the L* length must be determined to be the result of cracks with an orientation no greater than 30 degrees from axial; c) the L* criteria shall be limited to a maximum of 600 tube ends per steam generators di tubes qualifying as F* tubes.are not classified as L* tubes; e) a minimum of 3.1 inches of the tube into the tubesheet from_the top of tubesheet or bottom of the rolled transition, which ever is lower, shall be inspected using rotating pancake coil eddy current technique or an inspection method shown to give equivalent or better information on the orientation and length of axial cracks; )

f) a minimum aggregate of 1.74 inches plus allowance for eddy current measurement uncertainty, of sound roll expanded tube distance with no more than 1 band of tube degradation in the form of axial cracking (15 flaws of 0.5 inch or less in axial length), which is limited to less than 30 degrees i from the axial direction, must be found in the inspected ,

portion of the tubes or a minimum aggregate of 1.87 inches '

plus allowance for eddy current measurement uncertainty, sound roll expanded tube distance with no more than 2 bands of tube degradation in the form of axial-cracking (15 flaws of 0.5 inch or less in axial length), which is limited to l less than 30 degrees from the axial direction, must be found I in the inspected portion of the tube; and g) that remains in l'

, service. The allowance for eddy current uncertainty is documented in the steam generator eddy current inspection procedure.

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.6.5 Reports

a. Following each inservice inspection of steam generator tubes, the I number of tubes plugged, repaired or designated F*/ Lim.in each steam generator shall be reported to the Commission within 15 days of the completion of the inspection, plugging or repair effort.

b. The complete results of the steam generator tube and sleeve U inservice inspection shall be submitted to the Commission in a I Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection. This Special Report shall include:

1. Number and extent of tubes and sleeves inspected.

2. Location and percent of wall-thickness penetration for each indication of an imperfection.

3. Identification of tubes plugged or repaired.

c. Results of steam generator tube inspections which fall into Category C-3 shall be considered a REPORTABLE EVENT and shall be reported pursuant to 10CFR50.73 prior to resumptien of plant operation. The written report shall provide a description of investigations conducted to determine the cause of the tube degradation and corrective measures taken to prevent recurrence.

d. For implementation of the voltage-based repair criteria to tube support plate intersections, notify the staff prior to returning i the steam generator to service (Mode 4) should any of the following conditions arise:

1. If estimated leakage based on the projected end-of-cycle (or j if not practical, using the actual measured end-of-cycle) l voltage distribution exceeds the leak limit (determined from the licensing basis dose calculation for the postulated main

, steam line break) for the next operating cycle.

2. If circumferential crack-like indications are detected at the tube support plate intersections.

3. If indications are identified that extend beyond the confines of the tube support plate.

4. If indications are identified at the tube support plate elevations that are attributable to primary water stress corrosion cracking.

5. If the calculated conditional burst probability based on the projected end-of-cycle (or if not practical, using the actual , measured end-of-cycle) voltage distribution exceeds ,

1 x 10~, notify the NRC and provide an assessment of the l safety significance of the occurrence.

L' criteric i: applicable to Cycle 11 enly.

FARLEY-UNIT 2 3/4 4-13b AMENDMENT NO.

REACTOR COOLANT SYSTEM BASES

3. The tabe plugging limit continues to apply to the portion of the tube in the entire upper joint region and in the lower roll expansion. As noted above, the sleeve plugging limit applies to these areas also.

4. The tube plugging limit continues to apply to that portion of the d' tube above the top of the upper joint.

b. Laser Welded

1. Indications of degradation in the length of the sleeve between the weld joints must be evaluated against the sleeve plugging limit.

2. Indication of tube degradation of any type including a complete break in the tube between the upper weld joint ard the lower weld joint does not require that the tube be removed from service.

3. At the weld joint, degradation must be evaluated in both the sleeve and tube.

4. In a joint with more than one weld, the weld closest to the end of the sleeve represents the joint to be inspected and the limit of the sleeve inspection.

5. The tube plugging limit continues to apply to the portion of the tube above the upper weld joint and below the lower weld joint.

F* tubes do not have to be plugged or repaired provided the remainder of the tube within the tubesheet that is above the F* distance is not degraded. The F* distance is equal to 1.54 inches plus allowance for eddy current uncertainty measurement and is measured down from the top of the tubesheet or the bottom of the roll transition, whichever is lower in elevation.

L* is similar to F*; however, bands of axial degradation are allowed as long as sufficient non-degraded tubing is available to ensure structural and leakage integrity. L' ::iterien is only :pplicable f: " nit 2 Cycle 11.

Peccided belew i: the " nit 2 Cy:1: 11 :pecific L' criteri:n- The I* distance for a single band of degradation is 1,74 inches and for two bands of degradation is 1.87 Laches. Eddy current uncertakaty measuramant allowance must be added to these L* distances. The mav4=am length for any degradation band is 0.5 Laches. SBC has achninistratively limited the number of distinct degradation areas La the band to 15, although Westinghouse support documentation justifies up to 30 such areas.

EARLEY-UNIT 2 B 3/4 4-3b AMENDMENT NO. l

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REACTOR COOLAMT SYSTEM BASES

t'r. i t 2 Cyci 11 4

ifi: L' Crit:ricr.

r Paramctcr Ve-1-ee tiinimum dictance of SRE 2 . O ~' inchcc Maximum number Of distinct degradation arcas in a 6 i beed I i

i Maximum inclination angic .;ithin a singlc band 15 degrccc l 4 s Maximum crack length .30 inchec 4

Minimum dictancc of SRE frc the bor.tc= cf the 1.05 inchcc 4

trancition roll to th; top of the indication Steam generator tube inspections of operating plants have demonstrated the I capability to reliably detect wastage type degradation that has penetrated 20% l 4

of the original tube wall thickness.

1 Whenever the results of any steam generator tubing inservice inspection fall j into Category C-3, these results will be reported to the Commission pursuant  ;

to 10 CFR 50.73 prior to resumption of plant operation. Such cases will be l

' considered by the Commission on a case-by-case basis and may result in a 1 requirement for analysis, laboratory examinations, tests, additional eddy-current inspection, and revision to the Technical Specifications, if necessary.

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REACTOR COOLANT SYSTEM 3 3/4.4.6 STEAM GENERATORS LIMITING CONDITION FOR OPERATION 3.4.6 Each steam generator shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

I ', ACTION:

With one or more steam generators inoperable, restore the inoperable

%> generator (s) to OPERABLE status prior to increasing Tavg above 200*F.

I SURVEILLANCE REQUIREMENTS l 4.4.6.0 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements )

a of Specification 4.0.5. '

i 4.4.6.1 Steam Generator Sample Selection and Inspection - Each steam generator shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 4.4-1.

i 4.4.6.2.1 Steam Generator Tube # Sample Selection and Inspection - The steam

~ generator tube minimum sample size,. inspection result classification, and the corresponding action required shall be as specified in Table 4.4-2. The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.4.6.3 and the inspected tubes shall j be verified acceptable per the acceptance criteria of Specification 4.4.6.4.

The tubes selected for each inservice inspection shall include at least 3% of the total number of tubes in all steam generators. Selection of tubes to be

inspected is not affected by the F*/L* designation. When applying the l exceptions of 4.4.6.2.1.a through 4.4.6.2.1.c, previous defects or imperfections in the area repaired by sleeving are not considered an area requiring re-inspection. The tubes selected for these inspections shall be selected on a random basis except

, a. Where experience in similar plants with similar water chemistry j indicates critical areas to be. inspected, then at least 50% of the tubes inspected shall be from these critical areas.

b. The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:

1. All nonplugged tubes that previously had detectable wall penetrations greater than 20%.

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1. When referring to a steam generator tube, the sleeve shall be considered a part of the tabe if the tube has been repaired per Specification 4.4.6.4.a.9.

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1 FARLEY-UNIT 2 3/4 4-9 AMENDMENT NO.

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

Category Inspection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.

C-2 One or more tubes, but not more than li of the total tubes inspected are defective, or between Si and 10% of the total tubes inspected are degraded tubes.

C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.

Note: In all inspections, previously degraded tubes or sleeves must exhibit '

significant (greater than 10%) further wall penetrations to be included in the  !

above percentage calculations. I I

4.4.6.2.2 Steam Generator F*/L* Tube Inspection - In addition to the l I minimum sample size as determined by Specification 4.4.6.2.1, all F*/L* tubes l

will be inspected within the tubesheet region. The results of this inspection '

will not be a cause for additional inspections per Table 4.4-2. I 4.4.6.3 Ingpection Frequencies - The above required inservice inspections of steam generator tubes shall be performed at the following frequencies:

a. The first inservice inspection shall be performed after 6 Effective Full Power Months but within 24 calendar months of l initial criticality. Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection. If two consecutive inspections following service under AVT conditions, not including the preservice inspection, result in all inspection results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months,

b. If the results of the inservice inspection of a steam generator conducted in accordance with Table 4.4-2 at 40 month intervals fall in Category C-3, the inspection frequency shall be increased to.at least once per 20 months. The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of Specification 4.4.6.3.a; the interval may then be extended to a maximum of ence per 40 months.

c. Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.4-2 during the shutdown subsequent to any of the following conditions:

I FARLEY-UNIT 2 3/4 4-11 AMENDMENT NO.

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

6. Plugging or Repair Limit means the imperfection depth at or beyond which the tube shall be repaired (i.e., sleeved) or removed from service by plugging and is greater than or equal to 40% of the nominal tube wall thickness. This definition does not apply for tubes th6t meet the F*/L* l criteria. For a tube that has been sleeved with a mechanical joint sleeve, through wall penetration of greater s' than or equal to 31% of sleeve nominal wall thickness in the sleeve requires the tube to be remored from service by plugging. For a tube that has been sleeved with a welded joint sleeve, through wall penetration greater than or equal to 37% of sleeve nominal wall thickness in the sleeve between the weld joints requires the tube to be removed from service by plugging. This definition does not apply to tube support plate intersections for which the voltage-based repair criteria are being applied. Refer to 4.4.6.4.a.16 for the repair lindt applicable to these intersections.

7. Unserviceable describes the condition of a tube or sleeve 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 4.4.6.3.c, above.

8. Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg. For a tube that has been repaired by sleeving, the tube inspection should include the sleeved portion of the tube.

9. Tube Repair refers to mechanical sleeving, as described by Westinghouse report WCAP-ll178, Rev. 1, or laser welded sleeving as described by Westinghouse report WCAP-12672, which is used to maintain a tube in service or return a tube to service. This includes the removal of plugs that were installed as a corrective or preventive measure.

I EARLEY-UNIT 2 3/4 4-12a AMENDMENT NO.

<l l , l REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

10. Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to service to establish a baseline condition of the tubing. This inspection shall be performed after the field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used curing subsequent inservice inspections, j 11. F* Distance is the distance of the expanded portion of a tube which

! C' provides a sufficient length of undegraded tube expansion to resist l pullout of tne tube from the tubesheet. The F* distance is equal to ]

i 1.54 inches plus allowance for eddy current uncertainty measurement and 3 i

is measured down from the top of the tube sheet or the bottom of the {

roll transition, whichever is lower in elevation. The allowance for i

! eddy current uncertainty is documented in the steam generator eddy current inspection procedure. I

12. F* Tube is a tube: a) with degradation equal to or greater than 40%

below the F* distance, and b) which has no indication of imperfections greater than or equal to 20% of nominal wall thickness within the F*

distance, and c) that remains inservice.

If the above criteria cannot be met, then the L* tube criteria may be applied or the tube must be plugged or repaired.

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13. L* Length is the length of the expanded portion of the tube into the f

tube sheet from the bottom of the rolled transition or the top of the I tube sheet, which ever is lower, that has been determined to be .5 inches plus allowance for eddy current measurement uncertainty. The allowance for eddy current uncertainty is documented in the steam generator eddy current inspection procedure.

14. L* Tube: a) is a tube having degradation equal or greater than 40s through wall that is below the L* length and not degraded within the L* i length; b) the eddy current indication of degradation below the L*

length must be determined to be the result of cracks with an orientation no greater than 30 degrees from axial; c) the L* criteria shall be limited to a maximum of 600 tube ends per steam generator; d) tubes qualifying as F* tubes are not classified as L* tubes; e) a minimum of 3.1 inches of the tube into the tubesheet from the top of tubesheet or bottom of the rolled transition, which ever is lower, shall be inspected using rotating pancake coil eddy current technique or an inspection method shown to give equivalent or better information on the orientation and length of axial cracks; f) a minimum aggregate of 1.74 inches plus allowance for eddy current measurement uncertainty, of sound roll expanded tube distance with no more than 1 band of tube degradation in the form of axial cracking (15 flaws of 0.5 inch or less in axial length), which is limited to less than 30 degrees from the axial direction, must be found in the inspected portion of the tubes or a minimum aggregate of 1.87 inches plus allowance for eddy current measurement uncertainty, sound roll expanded tube distance with no more than 2 bands of tube degradation in the form of axial cracking (15 flaws of 0.5 inch or less in axial length), which is limited to less than 30 l degrees from the axial direction, must be found in the inspected portion of the tube; and g) that remains in service. The allowance for eddy current uncertainty is documented in the steam generator eddy current inspection procedure.

FARLEY-UNIT 2 3/4 4-12b AMENDMENT NO.

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.6.5 Reports

a. Following each inservice inspection of steam generator tubes, the number of tubes plugged, repaired or designated F*/L* in each l steam generator shall be reported to the Commission within 15 days of the completion of the inspection, plugging or repair effort.

b. The complete results of the steam generator tube and sleeve

%> inservice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection. This Special Report shall include:

1. Number and extent of tubes and sleeves inspected.

2. Location and percent of wall-thickness penetration for each indication of an imperfection.

3. Identification of tubes plugged or repaired.

c. Results of steam generator tube inspections which fall into Category C-3 shall be considered a REPORTABLE EVENT and shall be reported pursuant to 10CFR50.73 prior to resumption of plant operation. The written report shall provide a description of investigations conducted to determine the cause of the tube degradation and corrective measures taken to prevent recurrence.

d. For implementation of the voltage-based repair criteria to tube support plate intersections, notify the staff prior to returning the steam generator to service (Mode 4) should any of the following conditions arise:

1. If estimated leakage based on the projected end-of-cycle (or if not practical, using the actual measured end-of-cycle) voltage distribution exceeds the leak limit (determined from the licensing basis dose calculation for the postulated main steam line break) for the next operating cycle.

2. If circumferential crack-like indications are detected at the tube support plate intersections.

3. If indications are identified that extend beyond the confines of the tube support plate.

4. If indications are identified at the tube support plate elevations that are attributable to primary water stress corrosion cracking.

5. If the calculated conditional burst probability based on the projected end-of-cycle (or if not practical, using the actual measured end-of-cycle) voltage distribution exceeds 1 x 10", notify the NRC and provide an assessment of the safety significance of the occurrence.

FARLEY-UNIT 2 3/4 4-13b AMENDMENT NO.

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i REACTOR COGLANT SYSTEM I BASES i g _ _____ _

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3. The tube plugging limit continues to apply to the portion of the j tube in the entire upper joint region and in the lower roll expansion. As noted above, the sleeve plugging limit applies to l these areas also.

I 4. The tube plugging limit continues to apply to that portion of the tube above the top of the upper joint.

i b. Laser Welded l  %

1. Indications of degradation in the length of the sleeve between the weld joints must be evaluated against the sleeve plugging limit.

2. Indication of tube degradation of any type including a complete break in the tube between the upper weld joint and the lower weld joint does not require that the tube be removed from service.

3. At the weld joint, degradation must be evaluated in both the sleeve and tube.

4. In a joint with more than one weld, the weld closest to the end of the sleeve represents the joint to be inspected and the limit of the sleeve inspection.

5. The tube plugging limit continues to apply to the portion of the l tube above the upper weld joint and below the lower weld joint.

F* tubes do not have to be plugged or repaired provided the remainder of the l

tube within the tubesheet that is above the F* distance is not degraded. The F* dista.s3 is equal to 1.54 inches plus allowance for eddy current uncettainty measurement and is measured down from the top of the tubesheet or the aottom of the roll transition, whichever is lower in elevation.

L* is similar to F*; hotever, bands of axial degradation are allowed as long as sufficient non-degraded tubing is available to ensure structural and leakage integrity. The L* distance for a single band of degradation is 1.74 inches and Esr two bands of degradation is 1.87 inches. Eddy current l uncertainty measurement allowance must be added to these L* distances. The maximum length for any degradation band is 0.5 inches. SNC has administratively limited the number of distinct degradation areas in the band  !

to 15, although* Westinghouse support documentation justifies up to 30 such areas.

Steam generator tube inspections of operating plants have demonstrated the  !

capability to reliably detect wastage type degradation that has penetrated 204 l of the original tube wall thickness.

! Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be reported to the Commission pursuant to 10 CFR 50.73 prior to resumption of plant operation. Such cases will be l considered by the g;nedssion on a case-by-case basis and may result in a

! requirement for analysis, laboratory examinations, tests, additional eddy- l current inspection, and revision to the Technical Specifications, if necessary.

i FARLEY-UNIT 2 B 3/1 4-3b AMENDMENT NO. l

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1 Unit 1 and 2 Technical Specification Pages ,

1 for Elevated Tubesheet Laser Welded Sleeve 1

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RtACTCa C00LAJr? SYSTDI I

SURVe!LLANC aSOUIRDEDrTS (Contanued:

4.4.6.4 Acceptance Criteria

a. As used in this Specifications g

• 1.

!amerfectlen means an ennepties to the dimensions.

fantsk er conteur of a tube er sleeve free that required by fabrication drawings or speciftsations, J redy-everent testing indications beleev 20% of the neednal well csasidered asthickness, it detectable, may*ae imperfestions.

3.

• Deeradation means a service-induced cracking, vaStage wear er general correstem occurring on either itstee .

er outside of a tube er sleeve.

3.

Deeraded fuhe means a tube, imeluding the sleeve if the tube has been repaired, that contains imperfeettens greater thaa er equal to 20% of the nesdaal wall thickness caused by degradaties.

4.

4 Deeradaties means the pereestage of the tube er sleeve meti thiekasas affected or renewed by degradation.

N, f~ w S.

ese means the as taperfectica of such severity that it x blot., W dh w irw ***** i*i"'

plugging er repair limit, A tube er f'o va ch *l**"*

• d*#*** A* d*#***i'**

o r M h M 6 M cSh tt k h a}o d 6.

Flueetas or henair 'mt means the imperfection depth

( at er beyond ususa the tube shall he repaired (i.e.,

} b \ower *od d . b w m. % 3 Qtd sleeved) er removed from servies by plugging and is 6,\tN*dtd InhF WMdt.d SI8A/6/ greater them er egaal to 49% of the nominal tube wall

\.

• thiekness.

g e@ a;, o c ?W M,9 ,3 N ,r M fhe a tube that has been sleeved with a

[ moehenical joint sleeve, threagh wall penetration of pro *whed %c, M$ Meal sl ENC greater them er egual to all of sleeve naminal well f - thickness in the sleeve regetres the tube to be h renewed from service by pluggiag. For a tube that has A

tweeb Amgf o g ${c8WM Eg M5f

• been sleeved with a welded jetat sleeve

, through well.

gY penetraties greater than er equal to all of sleeve mentaal well thishness la the sleeve between the mid joints requires the tube to be renewed from service by plugging. This definities does met apply to tube support plate intersectisms for oedeh the weltage-based plugging criteria are heleg applied. Refer to 4.4.6.4.a.11 for the plugging 11adt app 11 sable to th e tat.r..ett.as. g s

7.

Unserviceshle describes the esadittee of a tube er  !

sleeve if it leaks or eestains a defeat large enough j to affect its structorsa 1stegrity la the event of as Operating basis Earthquake, a less-et-eoolaat -

accident, or a steam line or feedwater line break as speettled in 4.4.6 3.s above.

yAnt.tY-UNIT 1 3/4 4-12 AMDetsert No.!",'O Oir 66,w s 117 i

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h bg g ke., s. toe rase.st a.

j M c, go essas .. ins eette. o f the -

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, y p

generater tune free the pean,t of entry

{ ;g ( cold lot.A For a tube that has been repatred by sleeving,portion sleeved the tubeof taapection the tube. should include the y S.

) Tube nesa1_r refers to mechanical sleeving, as O descateed by Westinghouse report WCAP-1117s Rev. 1, ,

y er laser welded sleeving, as described by eestinghouse e

[ report WChP-12612.Auhteh is used to asintain a tube in s . servaes the resseval er retura a tube of paves that to service.

were ins This includes ge/4./b corrective er preventave measure. talled as a 14.

Preservice length of each Inseesties assas tube la eset steam en inmection generator performedof t by oddy surgent teshaigues prior to service to establish a baselias esadities of the Thistubing.

Qf 3 f hydrostatie test and prior to initial POWtA 0FEAAT!QIl bhy4 during subsequent inservice taspections.using

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fj Tube Summert Plate 91mmaine N't is used for the disposattee of a stoaa geacrator tube for seatinued service that is esportensieg outside diameter stress the tube support plates.eerresten essenlag eenfiaed with These criteria are applicable for the Feesteenth operattag eyele only.

At tube support plate intersections, the repair limit is based on esistaintag stoes generator tube

. servissability as described telews a.

Degradaties attributed to outside diameter stress corresten eracking withis the bounde of the tube support plate with behbia voltage less than er egual to 2.0 volts will be allowed to remaia in servies.

b. Degradaties attributed to outside diameter stress corresten eteeking withis the bounds of the tube support plate with a bobbia voltage greater than 2.0 welts will be repaired or plugged eseept as seted La 4.4.4.4.a.11.s below. 1

• c. Indications of poteettal degradatica attributed to outside diameter stress eerresten ersettag withis the beends of the tube support plate with a hobbia voltage greater than 2.0 volts but less i thaa er egnal to S.6 veits any remata la servtce if a rotattag peasake esal laspeetles does not deteet degradaties. Tadioations of outside diameter stress corroeien erasking degresstion with a babbia voltage greater than S.6 volts will be plugged es repaired.

rnssJfy.guyF 1 3/4 4-12s ApWIDWT NO.66rW.117

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! .' REACTOR COOLANT SYSTEM l

! SURVEILLANCE REQUIREMENTS (Continued)

! 6, Plugging or Repair Limit means the imperfection depth at or i beyond which the tube shall be repaired (i.e., sleeved) or removed from service by plugging and is greater than or equal to 40% of the nominal tube wall thickness. This definition does not apply for tubes that meet the F*/L* l criteria. For a tube that has been sleeved with a s'

mechanical joint sleeve, through wall penetration of greater than or equal to 31% of sleeve nominal wall thickness in the sleeve requires the tube to be removed from service bv plugging. For a tube that has been sleeved with a welded joint sleeve, through wall penetration greater than or equal to 37% of sleeve nominal wall thickness in the sleeve between the weld jointa requires the tube to be removed from service by plugging. This definition does not apply to tube support plate intersections for which the voltage-based repair criteria are being applied. Refer to 4.4.6.4.a.16 for the repair limit applicable to these intersections. For a tube with an imperfection or flav La the tubenheet below the lower joint of an installed elevated laser welded sleeve, no repair or plugg1ng is required provided the installed sleeve meets all sleespd tube Laspection requirements.

7 Unserviceable describes the condition of a tube or sleeve 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 4.4.6.3.c, above.

8. Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg. For a tube with a tube sheet sleeve Laeta 11ed, the potat of entry is the botteen of the tube sheet sleeve below the lower sleeve joint. For a tube that has been repaired by sleeving, the tube inspection should include the sleeved portion of the tube.

9. Tube Repair refers to mechanical sleeving, as described by Westinghouse report WCAP-lll?8, Rev. 1, or laser welded sleeving as described by Westinghouse report WCAP-12672, or, for elevated sleeves, Southern Mnnelear letter dated August 23, 1996, which is used to maintain a tube in service or return a tube to service. This includes the removal of l plugs that were installed as a corrective or preventive I measure.

I FARLEY-L* NIT 2 3/4 4-12a AMENDMENT NO.

I REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

15. Tube Expansion is that portion of a tube which has been I increased in diameter by a rolling process such that no l crevice exists between the outside diameter of the tube and the hole in the tubesheet. Tube espansion also refers to i that portion of a sleeve which has been Lacreased La l diameter by a ro11 Lag process such that no crevice exists l between the outside diameter of the sleeve and the parent steam generator tube.

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16. Tube Support Plate Repair Limit is used for the disposition I

of an alloy 600 steam generator tube for continued service l that is experiencing predominately axially oriented outside diameter stress corrosion cracking confined within the thickness of the tube support plates. At tube support plate l intersections, the repair limit is based on maintaining steam generator tube serviceability as described below:

a. Steam generator tubes, whose degradation is attributed l to outside diameter stress corrosion cracking within the bounds of the tube support plate with bobbin j voltages less than or equal to the lower voltage repair limit [2.0 volts), will be allowed to remain in service.

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b. Steam generator tubes, whose degradation is attributed l to outside diameter stress corrosion cracking within the bounds of the tube support plate with a bobbin l voltage greater than the lower voltage tepair limit

[2.0 volts), will be repaired or plugged except as j noted in 4.4.6.4.a.16.c below.

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c. Steam generator tubes, with indications of potential l degradation attributed to outside diameter stress l l corrosion cracking within the bounds of the tube support plate with a bobbin voltage greater than the

! lower voltage repair limit [2.0 volts] but less than l or equal to the upper voltage repair limit *, may remain in service if a rotating probe inspection does

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not detect degradation. Steam generator tubes, with indications of outside diameter stress corrosion l cracking degradation with a bobbin voltage greater I than the upper voltage repair limit *, will be plugged l or repaired.

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• The upper voltage repair linit is calculated according to the

, n.ethodology in Generic Letter 95-05 as supplemented.

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, FARLEY-UNIT 2 3/4 4-13 AMENDMENT NO.

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4 REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.6.4 Acceptance Criteria

a. As used in this Specification:

1. Imperfection means an exception to the dimensions, finish or contour of a tube or sleeve from that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal wall thickness, if detectable, may be considered as imperfections.

2. Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube or sleeve.

3. Degraded Tube means a tube, including the sleeve if the tube has been repaired, that contains imperfections greater than or equal to 20% of the nominal wall thickness caused by degradation.

4. 4 Degradation means the percentage of the tube or sleeve wall thickness affected or removed by degradation.

5. Defect means an imperfection of such severity that it exceeds the plugging or repair limit. A tube or sleeve containing a defect is defective.

6. Plugging or Repair Limit means the imperfection depth at or beyond which the tube shall be repaired (i.e., sleeved) or removed from service by plugging and is greater than or equal to 40% of the nominal tube wall thickness. For a tube that has been sleeved with a mechanical joint sleeve, through wall penetration of greater than or equal to 31% of sleeve nominal wall thickness in the sleeve requires the tube to be removed from service by plugging. For a tube that has been sleeved with a welded joint sleeve, through wall penetration greater than or equal to 37% of sleeve nominal wall thickness in the sleeve between the weld joints requires the tube to be removed from service bv plugging.

This definition does not apply to tube support plate intersections for which the voltage-based plugging criteria are being applied.

Refer to 4.4.6.4.a.11 for the plugging limit applicable to these intersections. For a tube with an imperfection or flaw in the tube sheet below the lower joint of an installed elevated laser welded sleeve, no repair or plugging is required provided the installed sleeve meets all sleeved tube inspection requirements.

7. Unserviceable describes the condition of a tube or sleeve 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 4.4.6.3.c, above.

FARLEY-UNIT 1 3/4 4-12 AMENDMENT NO.

REACTOR CCOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Cor.tinued)

8. Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg. For a tube with a tubesheet sic 2ve installed, the point of entry is the bottom of

' the tube sheet sleeve below the lower sleeve joint. For a tube that has been ropaired by sleeving, the tube inspection should include the sleeved portion of the tube.

I  %>

9. Tube Repair refers to mechanical sleeving, as described by Westinghouse report WCAP-11178, Rev. 1, or laser we3ded sleeving, as described by Westinghouse report WCAP-12672, or, for elevated sleeves, routhern Nuclear letter dated August 23, 1996, which is used to maintain a tuce in service or retuin a cube to service.

This includes the removal of plugs that were installed as a corrective or preventive measure.

10. Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to service to establish a baseline cendition of the tubing. This inspection shall be performed after the field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.

11. Tube Support Plate Plugging Limit is used for the disposition of a steam generator tube for continued service that is experiencing outside diameter stress corrosion cracking confined within the thickness of the tube support plates. These criteria are applicable for the Fourteenth operating cycle only. At tube support plate intersections, the repair limit is bated on maintaining steam generator tube serviceability as described i below:

a. Degradation attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with bobbin voltage less than or equal to 2.0 volts will be allowed to remain in service,

b. Degradation attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with a bobbin voltage greater than 2.0 volts will be repaired or plugged except as noted in 4.4.6.4.a.11.c below.

c. Indications of potential degradation attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with a bobbin voltage greater than 2.0 volts but less than or equal to 5.6 volts may remain in service if a rotating pancake coil inspection does not detect degradation. Indications of outside diameter stress corrosion cracking degradation with a bobbin voltage greater than 5.6 volts will be plugged or repaired.

FARLEY-UNIT 1 3/4 4-12a AMENDMENT NO.

-. . = _ __- -.

REACTOR CCOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

6. Pluqqing or Repair Limit means the imperfection depth at or beyond which the tube shall be repaired (i.e., sleeved) or removed from service by plugging and is greater than or equal to 40% of the nominal tube wall thickness. This definition does not apply for tubes that meet the F*/L*

criteria. For a tube that has been sleeved with a e

mechanical joint sleeve, through wall penetration of greater than or equal to 31% of sleeve nominal wall thickness in the sleeve requires the tube to be removed from service by plugging. For a tube that has been sleeved with a welded

' joint sleeve, through wall penetration greater than or equal to 37% of sleeve nominal wall thickness in the sleeve s

between the weld joints requires the tube to be removed from 4

service by plugging. This definition does not apply to tube i

support plate intersections for which the voltage-based repair criteria are being cpplied. Refer to 4.4.6.4.a.16 for the repair limit applicable to these intersections. For a tube with an imperfection or flaw in the tubesheet below l

the lower joint of an installed elevated laser welded '

sleeve, no repair or plugging is required provided the installed sleeve meets all sleeved tube inspection requirements.

l

7. Unserviceable describes the condition of a tube or sleeve if it leaks or contains a defect large enough to affect its I 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 4.4.6.3.c, above. I l

8. Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg. For a tube with a tube sheet sleeve installed, the point of entry is the bottom of the tube sheet sleeve below the lower sleeve joint. For a tube that has been repaired by sleeving, the tube inspection should include the sleeved j portion of the tube. I

9. Tube Repair refers to mechanical sleeving, as described by Westinghouse report WCAP-11178, Rev. 1, or laser welded sleeving as described by Westinghouse report WCAP-12672, or, for elevated sleeves, Southern Nuclear letter dated August 23, 1996, which is used to maintain a tube in service or return a tube to service. This includes the removal of plugs that were installed as a corrective or prever.tive measure.

FAPLEY-UNIT 2 3/4 4-12a AMENDMENT NO.

tl 6

' I l REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

15. Tube Expansion is that portion of a tube which has been 1 l increased in diameter by a rolling process such that no )

i crevice exists between the outside diameter of the tube and l l

the hole in the tubesheet. Tube expansion also refers to that portion of a sleeve whien has been increased in l

diameter by a rolling process such that no crevice exists between the outside diameter of the sleeve and the parent steam generator tube.-

U

16. Tube Support Plate Repair Limit is used for the disposition of an elloy 600 steam generator tube for continued service that is experiencing predominately axially oriented outside diameter stress corrosion cracking confined within the thickness of the tube support plates. At tube support plate intersections, the repair limit is based on maintaining steam generator tube serviceability as described below:

a. Steam generator tubes, whose degradation is attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with bobbin voltages less than or equal to the lower voltage repair limit (2.0 volts), will be allowed to remain in service.

b. Steam generator tubes, who'se degradation is attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with a bobbin i voltage greater than the lower voltage repair limit l (2.0 volts], will be repaired or plugged except as )

noted in 4.4.6.4.a.16.c below.

c. Steam generator tubes, with indications of potential degradation attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with a bobbin voltage greater than the i

lower voltage repair limit (2.0 volts) but less than I or equal to the upper voltage repair limit *, may remain in service if a rotating probe inspection does

, not detect degradation. Steam generator tubes, with indications of outside diameter stress corrosion cracking degradation with a bobbin voltage greater I than the upper voltage repair limit *, will be plugged or repaired, l

i The upper voltage repair limit is calculated according to the methodology in Generic Letter 95-05 as supplemented.

EARLEY-UNIT 2 3/4 4-13 AMENDMENT NO.

4