ML20238F476

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Proposed Tech Specs,Proposing New Repair Process for Plant OTSGs
ML20238F476
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 08/31/1998
From:
FLORIDA POWER CORP.
To:
Shared Package
ML20238F464 List:
References
NUDOCS 9809030382
Download: ML20238F476 (27)
v • d • e


Text

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _

l FLORIDA POWER CORPORATION I l CRYSTAL RIVER UNIT 3 i DOCKET NO. 50-302/ LICENSE NO. DPR-72 ,

I ATTACHMENT B l 1

LICENSE AMENDMENT REQUEST #235, REVISION 0 ONCE THROUGH STEAM GENERATOR TUBE SURVEILLANCE PROGRAM, TUBE REPAIR ROLL PROCESS I Proposed Technical Specification Change Pages (Strikeout / Shaded)

PR D 50 02 P PDR

Procedures, Programs and Manuals 5.6 5.6 Procedures, Programs and Manuals (continued) 5.6.2.10 Steam Generator (OTSG) Tube Surveillance Program Each OTSG shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program.

1. Each OTSG shall be determined OPERABLE during shutdown by selecting and in pecting t le :t the minimum number Of ~

OT.._S C.._: : i L insLect,.

on.!_cc.x.,fied in T;bl e 5.5.2 1. ~ir.f_6fhii..n9.W..ns.s_istiis

~ -

2. The OTSG tube minimum sample' size, inspection result classification, and the corresponding action required shall be as specified in Table 5.6.2-B1. The inservice inspection of 0TSG tubes shall be performed"at the frequencies.

specified in Specification 5.6.2.10.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 5.6.2.10.4. The tubes selected for each inservice inspection shall include at least 3% of the total number of tubes in eM Eihh OTSGs. The tubes selected for these inspections shill'^~be selected on a random basis except:

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

i

b. The first inscrvice in:pectica (:ubsequent to the prc:crvice in:pection) cf c;;h 0TSC : hall include:
1. All ncn
lug:;cd tube: thct previcu ly had l detecta:lc 0:11 penetration: (>20%),and
2. Tubc; in th::: arca: .;here experience h;; i indicated potential problemsr {
c. The cccad and third inservice in pection: m;y be 10 :

than full tube inspection by concentrating (:ciccting at least 50% of the tube; to be in :ccted) the inspection en thc : arca cf the tu:: :hect array and on thc;c portion cf the tubc where tubc; with ,

4mpe M eetion; werc previcu:ly found.  ;

6d. Tubes in specific limited areas which are distinguished by unique operating conditions or physical construction may be excluded from random samples if all such tubes (continued)

Crystal River Unit 3 5.0-13 Amendment No. 449

Procedures, Programs and Manuals 5.6

(

j 5.6 Procedures, Programs and Manuals 5.6.2.10- OTSG Tube Surveillance Program (continued) l in the specific area of an OTSG are inspected with the inspection result classification and the corresponding

. action required as specified in Table 5.6.242. No l credit will be taken for these tubes in meeting minimum l sample size' requirements. Degraded or defective tubes
found in these areas will not be considered in determining the inspection results category as long as

.the mode o.f degradation is unique to that area and not-randem in nature.

- Ee. Inservice tubes with pit-like IGA indications in the first span of the B OTSG,-identified in the 0TSG Inservice Inspection Surveillance Procedure, must be inspected with bobbin and Motorized Rotating Pancake Coil (MRPC) eddy current techniques from the lower tube sheet secondary face to the bottom of the first tube J support plate during each inservice inspection of the B OTSG. No credit is to be taken for this inspection in meeting minimum sample size requirements for the. random 3 inspection. Defective tubes found during this inspection are to be plugged or sleeved. Degraded or defective tubes found during this inspection are not to be considered in determining the inspection results 1

category for the random inspection, unless the degradation mechanism identified is a mechanism other than pit-like IGA.

59!jAll]tubesWi"chlhsviiiMen!Fspairsd bylthifFepiiEEFoll process (shallih'avejthe:newirolldareaexaminediduri.ng eacOinservicefinspectionONoldredit$is4toibeltaken forl t h i s si n specti on ki nj aeeti ng j mi n i mum Ls ampl e fs i ze..

requirementseforJthefrandomSinspectionh!Degradedio.._r defecti ve 1 tube ~sMound i duri ngi th i sfi n spect i on ; a resto ; lis pl ugged l orisl eeved. .1 D egraded tor / defecti ve t tubes Q found

.duri ng ; t h i ss i nspecti on ia re :i not :l toi bet con s i de red li n_

determi ni ng s t he W i n specti onj re s ul t sic atego ryiforithe randomiinspectione 1

l (continued)

Crystal River Unit 3 5.0-14 Amendment No. 458 l l

Procedures, Programs and Manuals 5.6 5.6 Procedures, Programs and Manuals 5.6.2.10 OTSG Tube Surveillance Program (continued)

3. The above-required inservice inspections of 0TSG tubes shall be performed at the following frequencies:
a. 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 all volatile treatment (AVT conditions, not including the "rescr")iceins-)ection,resultinallinspectionresults falline into tIie 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 inservice inspection of an OTSG, conducted in accordance with Table 5.6.2-31 or Table 5.6.2-32 requires a third sample inspection whose results fall in Category C-3, the inspection frequency shall be reduced to at least once per 20 months. The reduction in inspection frequency shall apply until a subsequent inspection demonstrates that a third sample inspection is not required.
c. Additional unscheduled inservice inspections shall be performed on each OTSG in accordance with the first sample inspection specified in Table 5.6.2-01 or Table 1 5.6.2-32 during the shutdown subsequent to any of the following conditions:
1. Primary-to-secondary tube leaks (not including )

leaks originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.12, l 2. A seismic occurrence greater than the Operating l Basis Earthquake, l 3. A loss-of-coolant accident requiring actuation of l the engineered safeguards, or i

4. A main steam line or feedwater line break.

T d .~ . 'IfLthe';;Lsour~ce of primary-to-secondaryTleskage in excess of ITS 3.4.12.is determined to1be.due'to degradation of

~

a-re the. pair roll,4100%

affected OTSG shall of the' havetubes with a repair roll in the Lrepair:rollJinspected. 4 If tthe:results of this inspection fall into the'C-3 ~ l category,tthen additionalerepair roll inspections..shall be performed:in:the unaffected 0TSG.

(continued)

Crystal River Unit 3 5.0-15 Amendment No. 449

Procedures, Programs and Manuals 5.6 5.6 Procedures, Programs and Manuals 5.6.2.10 OTSG Tube Surveillance Program (continued)

4. Acceptance criteria:
a. Vocabulary as used in this Specification:
1. Tubing or Tube means that portion of the tube or sleeve which forms the primary system to secondary system pressure boundary.
2. Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.
3. Degradation means a service-induced cracking, wastage, wear, or general corrosion occurring on either inside or outside of a tube.
4. Degraded Tube means a tube containing imperfection: degradation 120% throughwill of the nominal wall thimknbbb~ caused by degradatica excc:t wherc all such degradatica h:: .bcen sp;nned bn t;c . installation .cf 3;]ceve _ but%40%

tbroughwalliin ;thef pressures boun.dary;

5.  % Degradation N ThridghGill7means the 3ercentage of the tube (pressuresboundary) wall t1ickness affected or removed"bi~ degradation.
6. Defect mean; an imperfection of such ;cverity that it exceed; the plugging / lceving limit except where the imperfection h:: been spanned by the. _

installatica cf c 1ceve. ? Defective T+ube nieans

~l40%

attube:?containing throughwallfinithe 44ts; defect degradation:dary' pressure bonn 4

defec444e. "Any' tube which does not permit the 3assage of the eddy-current inspection probe shall se deemed a defective tube.

7. Pit-like Intergranular Attack (IGA) indication means a bobbin coil indication confirmed by  ;

Motorized Rotating Pancake Coil (MRPC) or other qualified inspection techniques to have a volumetric, pit-like morphology characteristic of IGA.

(continued)

Crystal River Unit 3 5.0-16 Amendment No. M8 l

l l

L.

Procedures, Programs and Manuals 5.6 f

5.6' Procedures, Programs and Manuals 5.6.2.10 OTSG Tube Surveillance Program (continued)

8. Plugging /Sle:ving Limit ::n: the extent of degr:d; tion beyond which the tube : hall be rc tered t :crviceability by the inst:llation Of
:10 ve er re: ved frs= ::rvice b ::u:: it ::y 5 :::: un:crvie :bic prior to the next in;pecti:n
nd i; :;;;l to 40*.' Of the n min:1 tub er :l eve w;11 thickne::. N :cre th:n five thou;;nd sleevc: ::y be in:talled in ::ch OTSC.

P106gi ng/Rephi FRisi tsmsin sithefsxtent?iffprisinfe boundary 1; degradation!beyond whichitheitube:shal.l.~

e i theri be fremoved ; fronijs erv i cel byli n stal l a t i on f of .

~

p1ugslorithelarsafeffdegradationishal_1Fbefremoisd f rom ; servi ce1( a ) newl pre s sure7 bou'nd ary i es tabl.i shed) ' ~ ~ ~

?

nsingkan! Approved?Rspair:?Tebhnique D The~

pl.ugging/repairklimi.t pressur:e: boundary;deg. radation;ps[40%jthroughwall36 Mill

9. Unserviceable describes the condition of a tube if l it leaks or contains a defect large enough to L affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a main steam.line or feedwater line break, as specified in 5.6.2.10.3.c, above.
10. Tube Inspection means an inspection of the entir 0TSG tube : f:r :: p ::ible. prssiUrsjb6uddsfy[

l .II S~ Appr6vid[Ripai ETeEhdi40sTiiesss?i5tsEhhiquiithaf

~

hasj bsent submi tied sto k eval uated i bidandJ accepted by?thelNRC1as?aimethodologitto5removeTdegradedior defecti Vej porti ons! ofsthe; pees surelbohndary n froi servi ce s and s tote s t abl i s h fa tnew ? pre s sure i boun% ry in;;: place whi chl hay? o ff !the e? been  ; deg QThe removed radedi fol

!ohl cki defecti vel por t i oni ~

ng fire' ApprossdlRepai --

ETech,ni qudsund sdeiaccept. abl. e,? f6r uset:

~

a)R Sl eeve?i hit hi l st i 06hi ni sicordinsiN) t hit hi B&W "proce's d ( ori method) [desc ri bed iLi nt repo rts BAW-2120P. INo moreithan!five!thousandisleeves may ' ' ~

bejirist'al.ledjinleach;0TSGF ' ' ' ~ ' '

bQ J'tubeshsetlipacdorda'ncejithith,ejFramatome"'! ni

~

(continued)

Crystal River Unit 3 5.0-l'7 Amendment No. M8 l

l Procedures, Programs and Monumis

5.6

.5.6 Procedures, Program Ond Manuals FF6Edis9iiE[ milli 6d)Idssifi6sdhiEpifditTBAWI 2303PMRevisjonj[3nyThi.sfrepajiRprocessmsy[bi performedroncelper4tubeMTh.e:Snewsrolharea mustitielfiee}offiinjisEfecti6ns3andidegradatiliii f.i n..?O_deM.._fo_d_t.h.i.f_

..m - m .

rep _a i d t_osm b_e.m?a_cc

e. .p_t_ab_l ef ~ ~
b. The OTSG shall be determined OPERABLE after completing the corresponding actions (plug or cle:v Fspsip all tubes all tub :exceeding cntaining thr the ugh plugging w / il."3F cks) required'byrigiliice
l. Table 5.6.2-G1 (and Table 5.6.2-32 if the provisions of Specification ~5.6.2.10.2.dli are ufilized). Defective tube: =y b re::tred in :Eccrd:nt with the S*W pr;;c:: (Or ::t;;d) :;u; valent to th ::thed d :cribed in report SAW 2120".

5.6.2.11 Secondary Water Chemistry Program This program provides controls for monitoring secondary water chemistry to-inhibit steam generator tube degradation and low

, pressure turbine disc stress corrosion cracking. The program l shall include:

a. Identification of a sampling schedule for the critical i- variables and control points for these variables;
b. Identification of the procedures used to measure the values of the critical variables; f

(continued) j Crystal ~ River Unit 3 5.0-17 Amendment No. MB j l

1 _ _ _ - - _ _ _ _ _ _ _ _.. . _ _ _ . - _ _ _ _ -- - - -

Procedures, Programs and Manuals 5.6

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s Crystal River Unit 3 5.0-24 Amendment No. 449 i

r

Procedures, Programs and Manuals 5.6 TABLE 5.6.2-01 (page 1 of 1)

OTSG TUBE' INSPECTION 1st Sample Inspection 2nd Sample Inspection 3rd Sample inspection Sample Size Result Action Result Action Result Action Required Required Required A minimum of C-1 None N/A N/A N/A N/A 3% & tubes per OTSG C-2 Plug or C-1 None N/A N/A repair 64eeve defective C-2 Plug or C-1 None tubes and repair inspect an +4+ eve additional defective 6% as tubes tubes and C-2 Plug or

in this inspect repair OTSG. additional NN "12% 45 tubes defective in this tubes.

OTSG.

C-3 Perform action for C-3 result of first sample.

C-3 Perform N/A N/A action for C-3 result i of first i sample. j l

i C-3 Inspect all The A44 None N/A N/A i tubes in other OTSGe I this OTSG, ame is  !

plug or C-1

repair

  • +**** The'other Perform N/A N/A defective Geme OTSGs action for j tubes, is C-2 result j inspect 6% C-2 but-ae of second BG tubes in dd!* fen:! sample.

the oesh gy.sg._ ,,

other OTSG, a and notify NRC per The'other Inspect all N/A N/A l 10CFR50.72 ?M !!!:n:t tubes in OTSG la C-3 this oesh j OTSG, plug or repair e4+ eve defective tubes, and notify NRC per 10CFR50.72.

-?'+ :n : :: n: r r - :f e? n: '- h: =' =e r :: t: f e? r: '=pri:d edn;
_.___.1
7. pe_:rg_

Crystal River Unit 3 5.0-25 Amendment No. M 9

Procedures, Programs and Manuals 5.6 TABLE 5.6.2-32 (page 1 of 1)

SPECIFIC LIMITED AREA INSPECTION ist Sample Inspection of a 2nd Sample Inspection of a

" Specific Limited Area" " Specific Limited Area" Sample Size Result Action Result Action Required Required 100% of area C-1 Ncne N/A N/A in both OTSGs C-2 Plug or N/A N/A repair steeve defective tubes.

C-3 Plug or N/A N/A repair s4eeve ,

defective I tubes.

100% of area C-1 None N/A N/A in one OTSG C-2 Plug or C1 None repair e4eeve defective tubes and . C2 Plug or inspe 100%

correspond. defective i ing area in tubes.

other OTSG C-3 Plug or repair e4 eve i defective i tubes. j C-3 Plug or C-1 None repair sleeve defective Plug or tubes and C-2 inspec 100%

correspond. defective ing area in tubes.

other OTSG.

C-3 Plug or repelt steeve defective tubes.

1 l

I l

Crystal River Unit 3 5.0-26 Amendment No. 449

Reporting Requirements 5.7 5.7 Reporting Requirements 5.7.2 Special Reports (continued)

The following Special Reports shall be submitted:

a. When a Special Report is required by Condition B or F of LC0 3.3.17, " Post Accident Monitoring (PAM)

%' Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

b. Any abnormal degradation of the containment structure detected during the tests required by the Containment Tendon Surveillance Program shall be reported to the NRC within 30 days. The report shall include a description of the tendon condition, the condition of the concrete (es)ecially at tendon anchorages), the inspection procedures, tie tolerances on cracking, and the corrective action taken.
c. Following each inservice ins)ection of steam generator (OTSG) tubes, the NRC shall se notified of the following prior to ascension into MODE 4:
1. Number of tubes plugged and sleeved Espigsdf
2. Crack-like indications in the first span [,}
3. An assessment of growth in the first span indications, and
4. Results of in-situ pressure testing, if performed. l B_Q.Risu1TK6f?OTSGEEU6sTGipiEf f6hiithifXfil lNnfif CifF#6^ffi[CI3' orted tolthe9NRCiphforsto@esumpticalof] plant ~'

'opepAt t oniMThi s isp6r t d h al l niroVi de1% de s crLip ti oni o f" ~

i nvesti g ati 6n si cond u cted h toi det ermi neit h'e sc au'seiofM tubi i degradationlanditorrectiyelmeasuresitaken[to} prevent ^" '

L recugencey 2Z E.a_F6116si 6fei.dhMsisi big h spsEf 6d:76fl0TSGithbis if tTh e gMFo f"ths"0TSG tub ~e~ inisFVi ce ~i~n s pict i on s h al l be submitted to the NRC within 90 daysi fcllcwing the completien of the in:;pection. The repbrt shall include:

1. Number and extent of tubes inspected, (continued) j Crystal River Unit 3 5.0-29 Amendment No. M8 l

Reporting Requirements 5.7 i 5.7 Reporting Requirements i

2. Location and percent of wall-thickness penetration for each indication of an imperfection,
3. Location, bobbin coil amplitude, and axial and circumferential extent (if determined) for each first span IGA indication, and
4. Identification of tubes plugged and tubes sleeved repairsd;iand s

-..e.ach;t.ube[

on;  ; pectfyltheirepair netho ology .

li ;d sd l i_mplement 5.7.2 Special Repcrt: (ccatinued)

Resul t cf OTSC tube in:pection; th:t f;11 into Categcry C 3 sh:11 be repcrted to the NRC pricr t0 rc umptica cf plant cperation. Thi repcrt shall provide : description of invc;tig: tion ccaducted te determinc c;uce of the tube degrad; tion :nd correctiv ::::ure; t; ken tc prevent recurrence.

Crystal River Unit 3 5.0-29A Amendment No. 168 l

FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NO. 50-302/ LICENSE NO. DPR-72 l

ATTACHMENT C LICENSE AMENDMENT REQUEST #235, REVISION 0 ONCE THROUGH STEAM GENERATOR TUBE SURVEILLANCE l l PROGRAM, TUBE REPAIR ROLL PROCESS l l

l Proposed Technical Specification Change Pages l (Revision Bars) l l

l l

l

l Procedures, Programs and Manuals 5.6 l 5.6 Procedures, Programs and Manuals l t

5.6.2.10 Steam Generator (OTSG) Tube Surveillance Program Each OTSG shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program.

l. Each OTSG shall be determined OPERABLE during shutdown by performing inservice inspection.
2. The OTSG tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 5.6.2-1. The inservice inspection I of OTSG tubes shall be performed at the frequencies specified in Specification 5.6.2.10.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 5.6.2.10.4. The tubes selected l for each inservice inspection shall include at least 3% of the total number of tubes in each OTSG. The tubes selected l l for these inspections shall be selected on a random basis except:

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

l b. Tubes in specific limited areas which are distinguished by unique operating conditions or physical construction t

may be excluded from random samples if all such tubes in the specific area of an OTSG are inspected with the l

inspection result classification and the corresponding action required as specified in Table 5.6.2-2. No l

credit will be taken for these tubes in meeting minimum sample size requirements. Degraded or defective tubes found in these areas will not be considered in determining the inspection results category as long as the mode of degradation is unique to that area and not r:r. dom ir, nature.

c. Inservice tubes with pit-like IGA indications in the l l first span of the B OTSG, identified in the OTSG i Inservice Inspection Surveillance Procedure, must be i inspected with bobbin and Motorized Rotating Pancake I Coil (MRPC) eddy current techniques from the lower tube sheet secondary face to the bottom of the first tube support plate during each inservice inspection of the B OTSG. He credit is to be taken for this inspection in 1 (continued)

Crystal River Unit 3 5.0-13 Amendment No.

I

i Procedures, Programs and Manuals 5.6

! 5.6 Procedures, Programs and Manuals l 1

l 5.6.2.10 OTSG Tube Surveillance Program (continued) meeting minimum sample size requirements for the random inspection. Defective tubes found durin inspection are to be plugged or sleeved.g this or Degraded defective tubes found during this inspection are not to be considered in determining the inspection results category for the random inspection, unless the degradation mechanism identified is a mechanism other than pit-like IGA.

d. All tubes which have been repaired by the repair roll process shall have the new roll area examined during each inservice inspection. No credit is to be taken for this inspection in meeting minimum sample size requirements for the random inspection. Degraded or defective tubes found during this inspection are to be plugged or sleeved. Degraded or defective tubes found during this inspection are not to be considered in determining the inspection results category for the random inspection.

The results of each bobbin coil sample inspection shall be classified into one of the following three categories:

NOTE----------- -------------------

In all inspections, previously degraded tubes whose degradation has not been spanned by a sleeve must exhibit significant 10%)

further wall calculations. penetrations to be included in then below perce(>

Cateaory 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 =re tubes, but rot mero than 1% of the total tubes inspected are defective, or between 5% and 10% of the total tubes inspected are degraded tunes.

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

l i

(continued)

Crystal River Unit 3 5.0-14 Amendment No.

Procedures, Programs and Manuals 5.6 5.6 Procedures, Programs and Manuals 5.6.2.10 OTSG Tube Surveillance Program (continued)

3. The above-required inservice inspections of OTSG tubes shall be performed at the following frequencies:
a. 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 all volatile treatment JAVT) conditions 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 inservice inspection of an OTSG, conducted in accordance with Table 5.6.2-1 or Table 5.6.2-2 requires l a third sample inspection whose results fall in Category C-3, the inspection frequency shall be reduced to at least once per 20 months. The reduction in inspection frequency shall apply until a subsequent inspection demonstrates that a third sample inspection is not required.
c. Additional unscheduled inservice inspections shall be performed on each OTSG in accordance with the first sample inspection specified in Table 5.6.2-1 or Table 5.6.2-2 during the shutdown subsequent to any of the ,

following conditions:

1. Primary-to-secondary tube leaks (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.12,
2. A seismic occurrence greater than the Operating Basis Earthquake,
3. A loss-of-coolant accident requiring actuation of tle er.gince.iad safegua,J , or i
4. A main steam line or feedwater line break,
d. If the source of primary-to-secondary leakage in excess of ITS 3.4.12 is determined to be due to degradation of a repair roll, 100% of the tubes with a repair roll in the affected 0TSG shall have the repair roll inspected.

If the results of this inspection fall into the C-3 category, then additional repair roll inspections shall be performed in the unaffected 0TSG.

i f (continued)

. Crystal River Unit 3 5.0-15 Amendment No.

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l Procedures, Programs and. Manuals 5.6 5.6 - Procedures, Programs and Manuals 5.6.2.10 OTSG Tube Surveillance Program (continued)

4. Acceptance criteria:
a. Vocabulary as used in this Specification:
1. Tubing or Tube means that portion of the tube or sleeve which forms the primary system to secondary system pressure boundary.
2. Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.
3. Degradation means a service-induced cracking, wastage, wear, or general corrosion occurring on either inside or outside of a tube.
4. Degraded Tube means a tube containing degradation 2 20% throughwall but < 40% throughwall in the pressure boundary.
5.  % Degradation /% Throughwall means the percentage of the tube (pressure boundary) wall thickness affected or removed by degradation.
6. Defective Tube means a tube containing degradation 140% throughwall in the pressure boundary. Any tube which does not permit the passage of the eddy-current ins defective tube. pection probe shall be deemed a
7. Pit-like Intergranular Attack (IGA indication )

means a bobbin coil indication conf)irmed by Motorized Rotating Pancake Coil (MRPC) or other qualified inspection techniques to have a volumetric, pit-like morphology characteristic of IGA.

8. Plugging / Repair Limit means the extent of pressure boundary degradation beyond which the tube shall either be removed from service by installation of plugs or the area of degradation shall be removed from service using an Appro(ved Repair Technique.a The new pressure boundar plugging / repair limit is 40% throughwall for all pressure boundary degradation.

(continued)

Crystal River Unit 3 5.0-16 Amendment No.

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Procedures, Programs and Manuals 5.6 5.'6 Procedures, Programs and Manuals 5.6.2.10 OTSG Tube Surveillance Program (continued)

9. ' Unserviceable describes the condition of a tube if it leaks.or contains a defect large enough to l affect its structural integrity in the event of an l

.0perating Basis Earthquake a loss-of-coolant accident, or a main steam line or feedwater line break, as specified in 5.6.2.10.3.c, above.

l

10. Tube Inspection means an inspection of the OTSG tube pressure boundary.
11 Approved Repair Technique means a technique that L. has been submitted to, evaluated by, and accepted i

by the NRC as a methodology to remove degraded or defective portions of the pressure boundary from service and to establish a new pressure boundary in place of the degraded or defective portions which have been removed. The following are Approved Repair Techniques and are acceptable for l- use:

l a) Sleeve installation in accordance with the B&W process (or method) described in report BAW-c 2120P. No more than five thousand sleeves may

-be installed in each OTSG.

b) Installation of 1" repair rolls in the upper tubesheet in accordance with the Framatome process described in report BAW-2303P, Re(or method) vision 3. This repair process may be performed once per tube. The new roll area must be free of imperfections and degradation l in order for the repair to be acceptable,

b. The OTSG shall be determined OPERABLE after completing the corresponding actions exceeding the plugging /repa(plug or repair all tubes ir limit

. 5.6.2-1 (and Table 5.6.2-2 if the pr)ovisions ofrequired by Table l Specification 5.6.2.10.2.b are utilized).

l There are a number of OTSG tubes that have the l: potential to exceed the tube plugging /sleesing limit as l'

a result of tube end anomalies. Defective tubes will be repaired or plugged during the next outage of sufficient duration. An evaluation has been performed

, which confirms that operability of the CR-3 OTSGs will l not be impacted with those tubes inservice.

L I

e (continued)

! I

!. Crystal River Unit 3 5.0-17 Amendment No.

Procedures, Programs and Manuals 5.6 5.6 Procedures, Programs and Manuals 5.6.2.11 Secondary Water Chemistry Program This program provides controls for monitoring secondary water chemistry to inhibit steam generator tube degradation and low pressure turbine disc stress corrosion cracking. The program shall include:

a. Identification of a sampling schedule for the critical variables and control points for these variables;
b. Identification of the procedures used to measure the values of the critical variables;
c. Identification of process sampling points which shall include monitoring the discharge of the co,ndensate pumps for evidence of condenser in leakage;
d. Procedures for the recording and management of data;
e. Procedures defining corrective actions for all off control point chemistry conditions; and
f. A procedure identifying the authority responsible for the interpretation of the data and the sequence and timing of administrative events, which is required to initiate corrective action.

-5.6.2.12 Ventilation Filter Testing Program (VFTP) required A' program testing of theshall be Room Control established to implement Emergency Ventilationthe following(CREVS)

System per the requirements specified in Regulatory Guide 1.52, Revision 2, 1978, and in accordance with ASME N510-1975 and ASME N509-1976,

a. Demonstrate for each train of the CREVS that an inplace test filters in of the hi h efficiency particulate air (HEPA) tested shows a penetra ion and system bypass < 0.05% when j accordance with Regulatory Guide 1.52, Revision 2, 1978, and in accordar.ce ~,,ith ASME N;10.1573 ai. a flowrate of 43,500 cfm i 10%.
b. Demonstrate for each train of the CREVS that an inplace test of the charcoal adsorber shows a penetration and system bypass < 0.05% when tested in accordance with Regulatory Guide 1.52, Revision 2, and ASME N510-1989 at the system flowrate of 43,500 cfm i 10%.

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(continued)  ;

! Crystal River Unit 3 5.0-18 Amendment No.

1

Procedures, Programs and Manuals' 5.6 5.6 Procedures, Programs and Manuals 5.6.2.12 .VFTP (continued)

c. Demonstrate for each train of the CREVS that a laboratory I test of a sample of the' charcoal adsorber, when obtained as described in Regulatory Guide 1.52, Revision 2, 1978, shows the methyl iodide penetration less than 1% when tested in accordance with Table 2 of Regulatory Guide 1.52, Revision 2 and ASME N509-1976 at a temperature of 80*C and 70% relative '

humidity.

d. Demonstrate for each train of the CREVS that the pressure drop across the combined HEPA filters and the charcoal adsorbers is s AP-6" water when tested in accordance with j Regulatory Guide 1.52, Revision'2, 1978, and ASME N510-1975 i at the system flowrate of 43,500 cfm i 10%.

l The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP l test frequencies.

l 5.6.2.13 Explosive Gas and Storage Tank Radioactivity Monitoring Program I

.This program provides controls for potentially explosive gas '

mixtures contained in the Radioactive Waste Disposal (WD) System, f the quantity of radioactivity contained in gas storage tanks or fed into the offgas' treatment system. The gaseous radioactivity quantities shall be determined following the methodology in Branch

" Postulated Radioactive Technical Release due Position (BTP) to Waste ETSB 11-5,k Gas System Lea or Failure". The liquid radwaste quantities-shall be determined in accordance with Standard Review Plan, Section 15.7.3, " Postulated Radioactive Release due to Tank Failures".

The program shall include:

a. The limits for concentrations of hydrogen and oxygen in the Radioactive Waste Disposal (WD) System and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria, (i.e.,

whether or not the system is designed to withstand a 1 hydrcgca explosion).

b. A surveillance program to ensure that the quantity of radioactivity contained in each gas storage tank and fed into the offgas treatment system is less-than the amount that would result in a whole body exposure of 2 0.5 rem to any individual in an unrestricted area, in the event of an uncontrolled release of the tanks' contents.

L The provisions of SR 3.0.2 and SR.3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program  ;

-surveillance frequencies.

(continued)

Crystal' River Unit 3 5.0-19 Amendment No.

_ __-._m m. mmmm_ __.m____ _-_ ,_m. -._

Procedures, Programs and Manuals 5.6 l

5.6 Procedures, Programs and Manuals i

TABLE 5.6.2-1 (page 1 of 1) l OTSG TUBE INSPECTION 1st Sample inspection 2nd Sample Inspection 3rd Sample Inspection Sample Site Result Action Result Action Result Action j Required Required Required j l.

A minimum of C1 None N/A N/A N/A N/A 3% tubes per i OTSG l l C-2 Plug or C1 None N/A N/A repair defective l tubes and C2 Plug or C-1 None I inspect an repair l

additional defective 6% tubes in tubes and C-2 Plug or this OTSG. inspect repair l

additional defective 12% tubes in tubes.

this OTSG.

C-3 Perform action for C-3 result of first sample.

C3 Perform N/A N/A action for C-3 result

, of first l sample.

C-3 Inspect all The other None N/A N/A tubes in OTSG is C-1 i this OTSG, l plug or repair defective The other Perform N/A N/A l

l tubes, OTSG is C 2 action for l

C- 2 .* ;:* '.t I inspect 6%

tubes in the of second other OTSG, sample, and notify NRC per 10CFR50.72 The other Inspect all N/A N/A OTSG is C-3 tubes in this OTSG, plug or repair defective l tubes, and notify NRC per 10CFR50.72.

l .. Crystal River Unit 3 5.0-24 Amendment No.

t

Procedures, Programs and Manuals 5.6 5.6 Procedures, Programs and Manuals TABLE 5.6.2-2 (page 1 of 1) l SPECIFIC LIMITED AREA INSPECTION ist sample Inspection of a 2nd Sample Inspection of a

" Specific Limited Area" " Specific Limited Area" Sample Size Result Action Result Action Required Required 100% of area C-1 None N/A N/A in both OTSGs C-2 Plug or N/A N/A repair l

defective tubes.

C-3 Plug or N/A N/A repair l

defective tubes.

100% of area C-1 None N/A N/A in one OTSG C-2 Plug or C-1 None repair defective l tubes and C-2 Plug or inspect 100% repair Of l defective correspond- tubes.

Ing area in other OTSG C-3 Plug or repair l

defective tubes.

i C-3 Plug or C1 None repair j defective tubes and C-2 Plug or inspect 100% repair Of l defective correspond- tubes.

Ing area in other OTSG.

C-3 Plug or repair l

defective tubes.

Crystal River Unit 3 5.0-25 Amendment No.

Procedures, Programs and Manuals i 5.6 5.6 Procedures, Programs and Manuals l

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THIS PAGE INTENTIONALLY LEFT BLANK l

Crystal River Unit 3 5.0-26 Amendment No.

Reporting Requirements 5.7 5.7 Reporting Requirements 5.7.2 Special Reports (continued)

The following Special Reports shall be submitted:

a. When a Special Report is required by Condition B or F of LCO 3.3.17, " Post Accident Monitoring (PAM)

Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

b. Any abnormal degradation of the containment structure detected during the tests required by the Containment Tendon Surveillance Program shall be reported to the NRC within 30 days. The report shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, and the corrective action taken.
c. Following each inservice inspection of steam generator (OTSG) tubes, the NRC shall be notified of the following prior to ascension into MODE 4:
1. Number of tubes plugged and repaired, l
2. Crack-like indications in the first span, l
3. An assessment of growth in the first span indications, and
4. Results of in-situ pressure testing, if performed.
d. Results of 0TSG tube inspections that fall into Category C-3 shall be reported to the NRC prior to resumption of plant operation. This report shall provide a description of investigations conducted to determine tne cause of tube degradation and corrective measures taken to prevent recurrence.

-e. Following each inservice inspection of 0TSG tubes, the complete results of the OTSG tube inservice inspection shall be submitted to the NRC within 90 days. The report shall  !

include:  !

1. Number and extent of tubes inspected, (continued) l Crystal River Unit 3 5.0-29 Amendment No.

L______

Reporting Requirements 5.7 5.7 Reporting Requirements l

5.7.2 Special Reports (continued)

2. Location and percent of wall-thickness penetration for each indication of an imperfection,
3. Location, bobbin coil amplitude, and axial and circumferential extent (if determined) for each first span IGA indication, and
4. Identification of tubes plugged and tubes repaired and specify the repair methodology implemented on each tube.

i i

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Crystal River Unit 3 5.0-29A Amendment No. j

FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NO. 50-302/ LICENSE NO. DPR-72 ATTACHMENT D LICENSE AMENDMENT REQUEST #235, REVISION 0 ONCE THROUGH STEAM GENERATOR TUBE SURVEILLANCE PROGRAM, TUBE REPAIR ROLL PROCESS List of Regulatory Commitments l

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l u___---___________-_

J U.S. Nuclear Regulatory Commission Attachment D 3F0898-01 Page1 ofI l'

L List of Regulatory Commitments The following table identifies those actions committed to by Florida Power Corporation in this document. Any other actions discussed in the submittal represent intended or planned actions by Florida Power Corporation. They are described for the NRC's information and are not regulatory commitments. Please notify the Manager, Nuclear Licensing, of any questions

. regarding this document or any associated regulatory commitnrnts.

l COMMITMENT DUE DATE l

The repair roll process will only be used in the upper Upon approval and tubesheet. implementation of LAR #235 Only the " single repair roll" methodology described in Upon approval and the qualification report will be implemented. implementation of LAR #235 The repair roll will be situated entirely below the Upon approval and existing roll. There will be no overlap with the existing implementation of roll. LAR #235 i

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