ML18012A536

Proposed Tech Specs,Amending TS 3/4.4.5, Sgs, & Associated Bases,To Add Sleeve Installation as Alternative to Tube Plugging for Repairing Degraded SG Tubes

ML18012A536
Person / Time
Site:	Harris
Issue date:	02/27/1997
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18012A538	List: ML18012A536 ML18022B001
References
NUDOCS 9703040393
Download: ML18012A536 (29)

Text

ENCLOSURE TO SERIAL: HNP-97-043 ENCLOSURE5 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT STEAM GENERATOR TUBE SLEEVING 970304039'3 970227 PDR ADOCK 05000400 P PDR

REACTOR COOLANT SYST"=8 3/4. 4. 5 S i eAM GENERATORS LIMITING CONOITION FOR OPERATION 3.4.5 Each steam generator shall be OPERABLE.

APPLICABILITY: MOGES l, 2, 3, and 4.

ACTION:

Nth.one or more steam generators inoperable, restore the inoperable generator{s) to OPERABLE status prior to increasing T above ZOO'F.

SURVEILLANCE REQUIREMENTS 4.4.5. 0 Each steam generator shall be demonstrated OPERABLE by parformance of the follmving augmented inservica inspection program and the requirenents of Specification 4.Q.5.

4.4.5.l Steam Generator Sample Selec ion and Insnection - Each steam generator shall be oetermlneo ourtng snutaawn oy se ectsng and inspec ing at least the minimum number of steam generators specified in Table 4.4-l.

4.4.5.2 Steam Generator Tub ample Selection and Insnection - The steam generator tuoe m~ncmum samp e ssza, cnspecuon resu t c ass> ication, and the corresponding action required shall be as specified in Tables 4.4-2 A and B.

The inservica inspection of steam generator tubes shgl be performed at the frequencies specified in Specification 4.4.5.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.5.4. The tubes selected for each inservfce inspection shall include at least 3" of 'the total number of tubes fn all steam generators; the tubes selected for these inspections shall 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 5P of the tubes inspected shall ba from these critical areas;

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

All nonpluggad tubes that previously had detectable wa11 penatrations {greater than 20"),

Tubes in those areas ~here experience has indicated Potential problems,+gF}~

%When referring to a steam generator tube, the sleeve shall be considered part of the tube if the tube has been repaired per Specification 4.4.5.4.a.l2.

SHEARON HARRIS - UNIT 1 3/4 4-33

SURVEILLANCE REOUIREtEVZS (Continued) 4.4.5.2 (Continued)

A tube inspection (pursuant to Specification 4,4.5.4a.B) shall be performed on each selected tube. If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and sub]ected to a tube inspection.

c. The tubes selected as the second and third samples (if Tables 4.4-2 A and B) during each inservice inspection may be sub-required by

)ected 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 cubes with imperfections were previously found, and

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

d. Each inspection shall include a sample of those tubes expanded in the preheater section of the steam generator. The first sample size, second sample size and subsequent inspection shall follow Table 4.4-2B.

e. In addition to the 3% sample, all tubes for which the alternate plugging criteria (W) has been previously applied shall be ec n the tubasheet regio

f. When applying the exceptions of 4.4.5.2.a through 4.4.5.2.e, previous defects or imperfections in the area covered by the sleeve pressure boundary are not considered an area requiring reinspection.

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

C-l Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective o C-2 One or more tubes, but not more than 1% of the total tubes inspected are defective, or between 5% and 10t of the total tubes inspected are degraded tubes.

C-3 Nore than 10% of the total tubes inspected are degraaed tubes or more than 1% of the inspected tubas are defective.

Ot.MvES Note: In all inspections, previously degraded tube t significant (greater than 10%) further wall penetrations to be included in the above percentage calculations.

SHEARON HARRIS - UNIT 1 3/4 4-14 Amendment No. 31

Technical Specification 3/4.4.5 Page >lf'%H+

Attachment "A", Insert at. 4.4.5-2 QO

3. At least~-,4 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 sleeve> and

SURVEILLANCE REOUIREfEVZS (Continued) 4.4,5,4

a. As used in this specification:

5Ll-6 6' eption to the dimensions, finish, or contour of a tubepfrom that, required by fabrication drawings or specifications. Eddy-current testing indications belov 20% of oR 5LKvE the nominal Pva3.1 thickness, if detectable, may be considered as imperfections; gener occurring on either inside or outside of a 3.

tube OK, 5LQBVB (QQQOixR on

~ 5&aVG lF QE"Q6E HMBEEA KS'SCGO>

g at I

or equal to 20% of the nominal vali thickness caused by degradation; C 5cal VG I

affected or removed by degra tion;

5. j~~ means the luggin an imperfec limit. A olE on 5LEEVP s severity that tubgcontaining a defect is defective it exceeds I

QePhi8ED,L omav Q~W uvlrf means the imperfection depth at o c the tuba shall hremoved from service and is equal to 404 of e no na e vali thickness es not, apply l to e area o a esheet region belov the pe stance provided the tuba is not degraded (i;e., no indications of lA0ea.t cracking) vithin the W distance.

aR ~vf FRTRM&K's' contains a defect large enough to affect its structural integ,-

rity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in Specification 4.4.5.3ces above; es 8(+~CM6 'TM <0 from the point of entry (hot leg side) co

-be d tmh<n~

t

~ufo ort tCgupEWAt=

e Ze g

~let EA'1Q581ilN4&l CABLED IWAOhl bF NC<<SEs ec on ng each tuba in each steam genarato performed by eddy current te ques pr or to se ce o es

" Lish a baseline condition of the tubing. This inspection shall be performed prior to initial POWER OPERATION using the equipment and techniques expected to

/ be used during subseguenu inseruiue insgeeuiens.

WN@ THE, DiEEdg. I g THE Tug@ H SgSKEA PEPttiggb SHEARON HARRIS - UNIT 1 3/4 4-16 Amendment No. 31

Technical Specification 3/4.4.5 Page 3/4 4-16 Attachment "B", Insert at 4.4.5.4.a.6 Plugging will be required for all tubes that have been repaired by sleeving where the sleeve imperfection is greater than 40% of nominal wall thickness. The portion of the tube and sleeve for which indications of wall degradation must be evaluated is that portion constituting the pressure boundary. The pressure boundary is defined as follows:

For a free span sleeve (both ends welded), the pressure boundary consists of that portion between the upper and lower weld centerlines.

ii. For a tubesheet area sleeve (lower end rolled), the pressure boundary consists of that portion between the upper weld centerline and the lower rolled joint centerline.

iii. For the tube, the pressure boundary consists of those portions of the tube above (and below for transition zone sleeves) the sleeve weld centerline.

c coo SURVEILLANCE REQUIREMENTS (Continued) the .tubesheet or the top of the last hardroll, whichever is lower (further into the tubesheet), that has been conservatively chosen to be 1.6 inches.

does not require the tube to be removed from service or repaired when the tube degradation exceeds the plugging limit so long as the degradation is in that portion of the tube from W to the bottom of the tubesheet.

This definition does not apply to tubes with degradation (i.e.,

indications o cracking) in the W distance.

12. ~Q~~ refers to sleeving, as described in Combustion Engineering Report CEN-630-P, Rev 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 r preventative measure.

SHEARON HARRIS - UNIT 1 3/4 4-16a Amendment No. 31

SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.4 u 0 <R

b. The steam generator shall be e z OPERABLE after completing the corresponding actions {plu all tubes exceeding the plugging limit and all tubes containing 'ough-wall cracks) required by Tables 4,4-2A and B.

4.4.5.5 EmxXCX

a. Within 15 days following the completion of each inse ce paction of steam generator tubes, the number of tubes pluggedgn each steam generator shall be reported to the Commission in a Special Report pursuant to Specification 6.9.2; WhhAQS 6LMVG+1

b. The complete results of the steam gene or 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. S c 1 Report shall include:

1. Number and extent of tube 4$ 5~evM

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

3. Identification of tubes plugged dg gEfAlPEDi C~ Results of steam generator tube inspections which fall into Category C-3 shall be reported in a Special Report pursuant to Specification 6.9.2 within 30 days and prior to resumption of plant operation.

This report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.

d. The results of the inspection of FA tubes shall be reported to the Commission in a report, prior to the restart of the unit following the inspection. This report shall include:

l. Identification of W tubes, and

2. Location and size of the degradation.

NRC appr'oval of this report is not required prior to restart.

SHEARON HARRIS - UNIT 1 3/4 4-17 Amendment No. 31

1ST SAHPLB INSPECTION 2ND SAHPLE INSPECTION 3RD SAHPLE INSPECTION Sample Size Result Action Required Result Action Required Result Action Required h minimum of C-1 None N/A N/A N/A N/A S Tubes per S.G. LC l.'& NiR.

C-2 Pluggefective tubes'-1 None N/A N/h and inspect additional 2S tubes in this S.G.

C-2 Pluggefective C-1 0 I Re&hk tubes'nd inspect additional. R 4S tubes in this S.G. C-2 Plug efective tubes'-3 Perform action for C-3 result of first sample C-3 Perform action for C-3 N/A N/A result of first, sample C-3 Inspect all tubes in hll other this S.G., plugge- S.G.s are None N/A N/A fective tubes'nd C-1 inspect 2S tubes in each other S.G. Some S.G.s Perform action for N/A N/A C-2 but no C-2 result of second additional sample S.G.s are C-3 Notification to NRC pursuant to Speci- Additional Inspect all tubes fication 4.4.5.5.c. S.G. is C-3 each S.G. and plu ~ggPPIQ defective tubes.'otification to NRC N/A N/h pursuant to Speci-fication. 4.4.5.5.c.

.S - fi vhere n is the number of steam generators inspected during an inspection.

• Defective tubes which falL under the Alternate Tube Plugging Criteria do not have to be plugged oR Ka fcqgEp,

TAOLE 4.4-28 SIEAH GEHERATDR IUGE IHSPECIION " TUBE DPANOEO IN PREIIEATER REGION 1ST SQQ'Lf IHSPECTlOH 2HO SAHPLE IHSPECTION Saap le .Size Result Action Required Result Action Required h alnlaua of S C-1 Cew<R H/h H/h of the tubas expanded in. C-2 Plu efective tubes C-1 OC R6f'AIR the prehaater and i spect all other section expanded tubes- in this C-2 Plug efective tubes Steaa Generator Perfora action for C-3 C-3 result of first sawple C-3 inspect all expanded hl I other Hone tubes in this 5tea QggGNN. S.G.s are Generator, plug afec- C" 1 tive tubas and nspect all expanded tubes in. One or uore each other Steaw S.G;s C"2 oK RGPhC.

Generator. but no addi- Plu efect ye tubas tional S.G.s are Hotif ication to HAC pursuant C-3 to Specification 4.4;5.5.c.

Additional S.G.

is C-3 Plug ec ve tubes.

Notification to tIRC pursuant to Specifica-tion 4.4.5.5.c.

9

= -X inspected during an inspection.

S where n is the nuabar of steaw generators n

BASES The plant is expected to be operated in a manner such that the secondary cool-ant vill be maintained within those chemistry limits found to result in negli-gible corrosion of the steam generator cubes. If the secondary coolant chemistry is not maintained within these limits, localized corrosion may likely result in seress corrosion cracking. The extant of cracking during plant operacion vould be limited by the limitation of seeam generator tube leakage between the Reactor Coolant Syseem and the Secondary Coolant System (reactor-to-secondary leakage 500 gallons per day per steam generator).

Cracks having a reactor-to-secondary leakage less than this limit during operation vill have an adequate margin of safety to withstand the loads lmposed during normal operation and by postulated accidents. Operating planes have demonstrated that reactor-to-secondary leakage of 500 gallons per day per steam generator can readily be dececced by radiation monitors of steam generator blovdown. Leakage in excess of this limit vill require plant shutdown and an unscheduled inspection, during, which the leaking tubes vill be located an eNtkao N, Wastage- are ualikely with proper chemistry treatment of the secondary coolant. However, even if a defect should develop in service, v 11 be found during scheduled inservice steam generator cube exaadnations.

it

)g, fig ugging will be required for all tubes vich imperfections exceeding the plugging limit of 40% of cha tuba nominal vali thickness. This plugging limit does noc apply to imperfectio'ns located belov the W region of any given tube.

The W criterion caa be applied only if the tube geometry in the region selected as the W distance falls vichin the analytical limits of WCAP-12B16.

Steam generacor tube inspeceions of operatiag plants have demonstrated the

~CRT capability to reliably detect degradation that has penetrated 20% of the original tube wall thickness.

Whenever the results of any steam generator tubing inservice inspection fall QQ into Category C-3, these results vill be reported to the Commission in a Special Report pursuant to Specification 4.4.5.5.c within 30 days and prior co resumption of plant operation. Such cases vill be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, teses, additional eddy-current inspection, and revision of the Technical Specifications, if necessary.

4 4 The RCS Leakage Detectioa Systems required by this specification are provided to monitor aad detect leakage from che reactor coolant pressure boundary.

These Deeectioa Systems are consistent with the recommendations of Regulatory Guide 1.45, 'Reactor Coolant Pressure Boundary Leakage Detection Systems," Hay 1973.

4 4 PRESSURE BOUNDARY LEAKAGE of any magnieude is unaccepeable since ic may be indicative of an impending gross 'failure of the pressure boundary. Therefore, the presence of aay PRESSURE BOUNDARY LEAKAGE requires the unit to be promptly placed in COLD SHUTDOWN.

SHEARON HARRIS - UNIT l B 3/4 4-3 Amendment No. 31

Technical Specification B3/4.4.5 Page 8 3/4 4-3 Attachment "C", Insert at B 3/4 4-3 A sleeved tube must be plugged ifa through wall penetration is detected in the sleeve that is equal to or greater than 40 percent of the nominal sleeve thickness. The plugging limit for the sleeve is derived from Reg. Guide 1.121 analysis and utilizes a 10% allowance for eddy current uncertainty and additional degradation growth. ~

REACTOR COOLANT SYST 3/4.4.5 STEAN GENERATORS LIHITING CONDITION FOR OPERATION 3.4.5 Each steam generator shall be OPERABLE.

APPLICABILITY: HODES 1, 2, 3, and 4.

ACTION:

With one or more steam generators inoperable, restore the inoperable generator(s) to OPERABLE status prior to increasing T,, above 200'F.

SURVEILLANCE REQUIREHENTS 4.4.5.0 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requi rements of Specification 4.0.5.

4.4.5. 1 Steam Generator Sam le Selection and Ins ection - 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.

4.4.5.2 Steam Generator Tube* Sam le Selection and Ins ection - The steam generator tube minimum sample size. inspection result classification. and the corresponding action requi red shall be as specified in Tables 4.4-2 A and B.

The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.4.5.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.5.4.

The tubes selected for each inservice inspection shall include at least 3X of the total number of tubes in all steam generators; the tubes selected for these inspections shall 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; 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 20K),

2. Tubes in those areas where experience has indicated potential problems,

• When referring to a steam generator tube, the sleeve shall be considered part of the tube if the tube has been repaired per Specification 4.4.5.4.a. 12.

SHEARON HARRIS - UNIT 1 3/4 4-13 Amendment No.

I P

r REACTOR COOLANT SYS STEAN GENERATORS SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.2 (Continued)

3. At least 20'f the total number of sleeved tubes in all three steam generators or all of the sleeved tubes in the enerator chosen for the inspection program, whichever is ess. These inspections will include both the tube and the sleeve, and

4. A tube inspection (pursuant to Specification 4.4.5.4a.8) shall be performed on each selecied tube.

tube does not permit the passage of the eddy Ifcurrent any selected probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.

C. The tubes selected as the second and third samples (if required by Tables 4.4-2 A and B) 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, and

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

Each inspection shall include a sample of those tubes expanded in the preheater section of the steam generator. The fi rst sample size, second sample size and subsequent inspection shall follow Table 4.4-2B.

e. In addition to the 3X sample, all tubes for which the alternate plugging criteria (F*) has been previously applied shall be inspected in the tubesheet region.

When applying the exceptions of 4.4.5.2.a through 4.4.5.2.e, previous defects or imperfections in the area covered by the sleeve pressure boundary are not considered an area requiring reinspection.

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

~Cate or Ins ection Results C-1 t Less h an 5K of the total tubes ins p ect ed are degraded tubes and none of the inspected tubes are defective.

C-2 One or more tubes, but not more than 1% of the total tubes insnected are defective.

or between 5K and 10K of the total tubes inspected are degraded tubes.

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

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

SHEARON HARRIS - UNIT 1 3/4 4-14 Amendment No.

a ~

lt REACTOR COOLANT SYST STEAM GENERATORS SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.4 Acce tance Criteria As used in this specification:

Im erfection means an exception to the dimensions, finish.

or con our of a tube or sleeve from that required by fabrication drawings or specifications. Eddy-current testing indications below 20K of the nominal tube or sleeve wall tiiickness, imperfections; if detectable, may be considered as De radation means a service-induced cracking, wastage, wear, or genera corrosion occurring on either inside or outside of a tube or sleeve; De as raded Tube means een a tube, including the sleeve if the tube repaired, containing imperfections greater than or equal to 20K of the nominal wall thickness caused by degradation; X De radation means the percentage of the tube or sleeve wa 1c ness affected or removed by degradation; Defect means an imperfection of such severity that exceeels the plugging 1imit. A tube or sleeve containing it a defect is defective; Plu in Limit means the imperfection depth at or beyond w sc e u e shall be repaired, (i.e. sleeved) or removed from service and is equal to 40K of the nominal tube wall thickness. Plugging will be required for all tubes that have been repaired by sleeving where the sleeve imperfection is greater than 40K of nominal wall thickness. The portion of the tube and sleeve for which indications of wall degradation must be evaluated is that portion constituting the pressure boundary. The pressure boundary is defined as follows:

For a free span sleeve (both ends welded), the ressure boundary consists of that por tion etween the upper and lower weld center lines.

ii. For a tubesheet area sleeve (lower end rolled),

the pressure boundary consists of that portion between the upper weld center line and the lower rolled joint center line.

iii. For the tube, the pressure boundary consists of those portions of the tube above (and below for tr ansition zone sleeves) the sleeve weld centerline.

The plugging limit does not apply to the area of the tubesheet region below the F* distance provided the tube is not degraded (i.e., no indications of cracking) within the F* distance.

SHEARON HARRIS - UNIT 1 3/4 4-16 Amendment No.

il g REACTOR COOLANT SYST STEAN GENERATORS SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.4 Acce tance Criteria (Continued) df'1 Unserviceable describes the condition of tt g a

ght ttt tube or sleeve ff if structural integrity in the event of an Operating Basis Earthquake. a loss-of-coolant accident, or a steam line or feedwater line break as specified in Specification 4.4.5.3c., above; Tube Ins ection means an inspection of the steam generator u e rom e 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:

Preser vice Ins ection means an inspection of the full length o eac u e 1n eac steam generator, including the sleeve if the tube has been repaired, performed by edify current techniques prior to service to establish a baseline conditson of the tubing. This inspection shall be performed rior to initial POMER OPERATION using the equipmenh and echniques expected to be used during subsequent inservice inspections.

10 F* Distance is the distance into the tubesheet from the face h 1 th t d f th 1 t h d 11. ht h is lower (further into the tubesheet) that has been conservatively chosen to be 1.6 inches.

Alternate Tube Plu in Criteria does not require the tube o e remove rom service or repaired when the tube degradation exceeds the plugging limit so long as the degradation is in that port>on of the tube from F* to the bottom of the tubesheet. This definition does not apply to tubes with degradation (i.e., indications of cracking) in the F* distance.

12 Tube Re air refers to sleeving. as described in Combustion ngsneenng Report CEN-630-P, Rev. Ol 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 preventative measure.

SHEARON HARRIS - UNIT 1 3/4 4-16a Amendment No'.

4 I

>~

4

REACTOR COOLANT SYS STEAN GENERATORS SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.4 Acce tance Criteria Continued

b. The steam generator shall be determined OPERABLE after completing the corresponding actions (plug or repai r all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Tables 4.4-2A and B.

4.4.5.5 ~Re orts

a. Within 15 days following the completion of each inservice inspection of steam generator tubes, the number of tubes plugged or repaired in each steam generator shall be reported to the Commission in a Special Report pursuant to Specification 6.9.2;

b. The complete results of the steam generator tube (including sleeves) 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, and

3. Identification of'ubes plugged or repai red.

c. Results of steam generator tube inspections which fall into Category C-3 sha11 be reported in a Special Report pursuant to Specification 6.9.2 within 30 days and prior to resumption of plant operation. This report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.

d. The results of the inspection of F* tubes shall be reported to the Commission in a report, prior to the restart of the unit following the inspection. This report shall include:

1. Identification of F* tubes, and

2. Location and size of the degradation.

NRC approval of this report is not requi red prior to restart.

SHEARON HARRIS - UNIT 1 3/4 4-17 Amendment No.

TABLE 4.4-2A STEAN GENERATOR TUBE INSPECTION 1ST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION Sam le Size Result Action Re uired Result Action Re ui red Result Action Re ui red A minimum of C-1 None N/A N/A N/A N/A S Tubes per S.G. Plug or repair C-1 None N/A N/A defective tubes*

and inspect Plug or repair . C-1 None additional 2S C-2 defective tubes*

tubes in this and inspect C-2 Plug or repair .

S.G: additional 4S defective tubes tubes in this S.G.

Perform action for C-3 C-3 result of first sam le Perform action C-3 for C-3 result N/A N/A of first sam le C-3 Inspect all tubes All other in this S.G.. S.G.s are None N/A N/A plug or repair . C-1 defective tubes*

and inspect 2S tubes in each other Some S.G.s Perform action for C-2 N/A . N/A S.G. C-2 but no result of second sample additional Notification to S.G.s are C-3 NRC pursuant to Specification Additional S.G. Inspect all tubes in 4.4.5.5.c. is C-3 each S.G. and plug or , N/A N/A repair defective tubes.*

Notification to NRC ursuant to ecification 4.4.5.5.c.

= -X where n is the number of steam generators S inspected during an inspection.

n Defective tubes which fall under the Alternate Tube Plugging Criteria do not have.to be plugged or repaired.

(/)

m CD TABLE 4.4-2B STEAM GENERATOR TUBE INSPECTION - TUBE EXPANDED IN PREHEATER REGION 1ST SAMPLE INSPECTION '2ND SAMPLE INSPECTION Sam le Size Result Action Re uired Result Action Re uired A minimum of S C-1 None N/A N/A of the tubes expanded in the Plug or repair defective tubes C-1 N/A preheater and inspect all other expanded tubes in this Steam Generator Plug or repair section defective tubes Perform action for-C-3 C-3 result of first I

sam le CD C-3 Inspect all expanded tubes All other None in this Steam Generator, plug S.G.s are C-1 or repair defective tubes and inspect all expanded tubes in One or more each other Steam Generator. S.G.s C-2 but Plug or repair no additional defective tubes S.G.s are C-3 Notification to NRC pursuant to Specification 4.4.5.5.c. Additional Plug or repair S.G. is C-3 defective tubes.

Notification to NRC ursuant to pecification 4.4.5.5.c.

S = -4 9

where n is the number of steam generators inspected during an inspection.

O n

S P

REACTOR COOLANT SYST BASES STEAM GENERATORS Continued 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 lant operation would be limited by the limitation of steam generator tube eakage between the Reactor Coolant. System and the Secondary Coolant System (reactor-to-secondary leakage = 500 gallons per day per steam generator ).

Cracks having a reactor-to-secondary leakage less than this limit during operation will have an adequate margin of safety to withstand the loads imposed during normal operation and by postulated accidents. Operating plants have demonstrated that reactor -to-secondary leakage of 500 gallons per day per steam generator can readily be detected bg radiatson monitors of steam generator blowdown. Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and repaired or plugged. I Wastage-type defects are unlikely with proper chemistry treatment of the secondary coolant. However. even if a defect should develop in service, will be found during scheduled inservice steam generator tube examinations.

it Repair or plugging will be required for all tubes with imperfections exceeding the plugging ]imit of 40K of the tube nominal wall thickness. This plugging limit, does not apply to imperfections located below the F* region of any given tube. The F* criterion can be applied only if the tube geometry in the region selected as the F~ distance falls within the analytical limits of WCAP-12816.

A sleeved tube must be plugged if a through wall penetration is detected in the sleeve that is equa] to or greater than 40 percent of the nominal sleeve thickness. The plugging limit for the sleeve is derived from Reg. Guide 1. 121 analysis and utilizes a 10K allowance for eddy current uncertainty and additional degradation growth. Steam generator tube inspections of operating lants have demonstrate the capability to reliably detect degradation that as penetrated 20K of the original tube wall thickness.

Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results we'll be reported to the Commission in a Special Report pursuant to Specification 4.4.5.5.c within 30 days and 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-current inspection, and revision of the Technical Specifications, if necessary.

3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6. 1 LEAKAGE DETECTION SYSTEMS The RCS Leakage Detection Systems required by this specification are provided to monitor and detect leakage from the reactor coolant pressure boundary.

These Detection Systems are consistent with the recommendations of Regulatory Guide 1.45, "Reactor Coolant Pressure Boundary Leakage Detection Systems,"

May 1973.

3/4.4.6.2 OPERATIONAL LEAKAGE PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending qross failure of the pressure boundary. Therefore, the presence of any PRESSURE BOUNDARY LEAKAGE requires the unit to be promptly placed in COLD SHUTDOWN.

SHEARON HARRIS - UNIT 1 B 3/4 4-3 Amendment No.

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ENCLOSURE TO SERIAL: HNP-97-043 ENCLOSURE6 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT STEAM GENERATOR TUBE SLEEVING

AFFIDAVITPURSUANT TO 10 CFR 2.790 I, lan C. Rickard, depose and say that I am the Director, Operations Licensing, of Combustion Engineering, Inc., duly authorized to make this affidavit, and have reviewed or caused to have reviewed the information which is identified as proprietary and referenced in the paragraph immediately below. I am submitting this affidavit in conjunction with the application of Carolina Power and Light Company and in conformance with the provisions of 10 CFR 2.790 of the Commission's regulations.

The information for which proprietary treatment is sought is contained in the following document:

CEN-630-P, Rev. 01, "Repair of 3/4" O.D. Steam Generator Tubes Using Leak Tight Sleeves," November 1996.

This document has been appropriately designated as proprietary.

I have personal knowledge of the criteria and procedures utilized by Combustion Engineering in designating information as a trade secret, privileged or as confidential commercial or financial information.

h Pursuant to the provisions of paragraph (b) (4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure, included in the above referenced document, should be withheld.

1. The information sought to be withheld from public disclosure, is owned and has been held in confidence by Combustion Engineering. It consists of the details concerning the fabrication process, material properties, and

surveillance data used to develop an approach to ascertain the embrittlement of reactor vessels.

2. The information consists of test data or other similar data concerning a process, method or component, the application of which results in substantial competitive advantage to Combustion Engineering.

3. The information is of a type customarily held in confidence by Combustion Engineering and not customarily disclosed to the public. Combustion Engineering has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence. The details of the aforementioned system were provided to the Nuclear Regulatory Commission via letter DP-537 from F. M. Stern to Frank Schroeder dated December 2, 1974. This system was applied in determining that the subject document herein is proprietary.

The information is being transmitted to the Commission in confidence under the provisions of 10 CFR 2.790 with the understanding that it is to be received in confidence by the Commission.

The information, to the best of my knowledge and belief, is not available in public sources, and any disclosure to third parties has been made pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence.

6. Public disclosure of the information is likely to cause substantial harm to the competitive position of Combustion Engineering because:

a. A similar product is manufactured and sold by major pressurized water reactor competitors of Combustion Engineering.

b. Development of this information by Combustion Engineering i equired tens of thousands of dollars and thousands of

manhours of effort. A competitor would have to undergo similar expense in generating equivalent information.

c. In order to acquire such information, a competitor would also require considerable time and inconvenience to develop the design, development, and installation process for a welded sleeve for repairing 3/4 inch O.D. steam generator tubes.

The information consists of the design, development, and installation process for a welded sleeve for repairing 3/4 inch O.D. steam generator tubes, the application of which provides a competitive economic advantage. The availability of such information to competitors would enable them to modify their product to better compete with Combustion Engineering, take marketing or other actions to improve their product's position or impair the position of Combustion Engineering's product, and avoid developing similar data and analyses in support of their processes, methods or apparatus.

e. In pricing Combustion Engineering's products and services, significant research, development, engineering, analytical, manufacturing, licensing, quality assurance and other costs and expenses must be included. The ability of Combustion Engineering's competitors to utilize such information without similar expenditure of resources may enable them to sell at prices reflecting significantly lower costs.

Use of the information by competitors in the international marketplace would increase their ability to market nuclear steam supply systems by reducing the costs associated with their technology development. In addition, disclosure would have an adverse economic impact on Combustion

Engineering's.potential for obtaining or maintaining foreign licensees.

Further the deponent sayeth not.

lan . rd Director, Operations Licensing Sworn to before me this ~ day of 1997 Notary,.Public My commission expires: PS/ 'P

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