ML20069B471

Proposed TS 3/4.4.5 Re Steam Generators

ML20069B471
Person / Time
Site:	Byron, Braidwood
Issue date:	05/20/1994
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML19304C174	List: ML20069B441 ML20069B471 ML20069B476
References
NUDOCS 9405270232
Download: ML20069B471 (18)

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ATTACHMENT 2a .

PROPOSED CHANGES TO APPENDIX A-TECHNICAL SPECIFICATIONS FOR FACILITY OPERATING LICENSES NPF-37 and NPF BYRON-Revised Pages: 3/4 4 -13* '

3/4 4 -14 3/4 4 -15*

3/4 4 -16 3/4 4 -17 3/4 4 -18*

3/4 4 ~-19*

B 3/44-3 Pages indicated with an asterisk (*) are not being revised rand are only included for convenience.

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PDR -ADOCK-05000454 PDR P

F ~ REACTOR COULANT SYSILM 3 /4 ; 4.5 STEAM GENERATORS -

LIMITING CONDITION FOR OPERATION 3.4.5 Each steam generator shall be OPERABLE.

APPLICABILITY: M0' DES 1, 2, 3 and 4.

ACTION:

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

SURVEILLANCE RE0VIREMENTS 4.4.5.0 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.

4.4.5.1 Steam Generator Samole Selection and Insoection - 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

• Samole Selection and Insoection - 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 fre-quencies 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. When applying the expectations of 4.4.5.2.a through 4.4.5.2.c, previous defects or imperfections in the area repaired by the sleeve _are not considered an area-requiring reinspection. The tubes selected for each inservice inspection shall include at least 3% 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;

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

• 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 4.4.5.4.a.10.

BYRON - UNITS 1 & 2 3/4 4-13 AMENDMENT NO, 58 m

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REACTOR COOLANT SYSTEM a SURVEILLANCE REOUIREMENTS (Con 2inuedi q

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1) All tubes that previously had detectable tube wall penetrations greater than 20% that have not been plugged or sleeved in'the affected area, and all tubes that previously had detectable sleeve wall penetrations that have not been plugged,

2) Tubes in those areas where experience has indicated potential probl ems,

3) At least 3% of the total number of sleeved-tubes in all four 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-  ;

4) A tube inspection (pursuant to Specification 4.4.5.4a.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 inspection,.

this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspectionj mui

'A 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, and ,

2) The inspections include those portions of the tubes where ,

imperfections were previously found. '

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

Cateoory 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 riot more' than 1% 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 tubes or more than 1% of the inspected tubes are defective.

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

BYRON - UNITS 1 & 2 3/4 4-14 AMENDMENT NO. 58

INSERT A

5) .in addition to the sample selection required in 1 - 4 above, all tubes which remain in service due to the application of the F* criteria will be inspected in the tubesheet region.

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REACTOR COOLANT-SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.3 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 interva'is of not less than 12 nor more than 24 calendar months after.the previous inspection. If two consecutive inspections, not including the pre-service inspection, result in all inspection results falling into the C-1 category or if two consecutive inspections demonstrate that pre'-

viously 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 4.4.5.3a. ; the interval may then be extended to a maximum of once per 40 months; and

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:

1) Reactor-to-secondary tube leaks (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.6.2c., or

2) A seismic occurrence greater than the Operating Basis Earthquake,-

or

3) A Condition IV loss-of-coolant accident requiring actuation of the Engineered Safety Features, or

4) A Condition IV main steam line or feedwater line break.

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BYRON - UNITS 1 & 2 3/4 4-15

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REACTOR COOLANT SYSTEM SURVEILLANCE RE0VIREMENTS (Continued) 4.4.5.4 Acceptance Criteria

a. As used in this specification:

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

2)

Dearadation means a service-induced cracking,

wastage, wear or general corrosion occurring on either inside or outside of a tube or sleeve; l

3) Dearaded Tube means a tube or sleeve containing unrepaired imperfections greater than or equal to 20% of.the nominal tube or sleeve wall thickness caused by degradation;

4)  % Dearadation means the percentage of the tube or sleeve wall l thickness affected or removed by degradation;

5) Defect means an imperfection of such severity that it exceeds the plegging or repair limit. A tube or sleeve containing an unrepaired defect is defective;

6) Pluaaina or Repair Limit means the imperfection depth at or beyond which the tube shall be removed from service by plugging l or repaired by sleeving in the affected area. The plugging or repair limit i erfection epitrhegual to 40% of the nominal wall thicknes .IusEer 8)

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7) Unserviceable describes the condition of a tube if it leaks or 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 4.4.5.3c., above;

8) Tube Inspection means ar, 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 shall include the sleeved portion of the tube, and 4

BYRON - UNITS 1 & 2 3/4 4-16 AMENDMENT NO. 58 8.

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For Unit 1, this definition does not apply to defects in the tubesheet  !

that meet the criteria for an P tube; t

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REACT 04 COOLANT SYSTEM.

SURVEILLANCE RE0VIREMENTS (Continued)

9) Preservice Insoection 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 t'he tubing. This inspection shall be performed prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections

10) Tube Repair refers to a process that reestablishes tube serviceability. Acceptable tube repairs will be performed by the following processes:

a) Laser welded sleeving as described by Westinghouse report WCAP-13698, Rev. 1, or b) Kinetic welded sleeving as described by Babcock & Wilcox Topical Report BAW-2045PA, Rev. 1.

Tube repair includes the removal of plugs that were previously installed as a corrective or preventative measure. A tube inspection per 4.4.5.4.a.8 is required prior to returning previously plugged tubes to service.

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The steam generator shall be determined OPERABLE after completing d the corresponding actions (plug or repair in the affected area all tubes exceeding the plugging or repair limit) required by Table 4.4-2.

4.4.5.5 Reports

a. Within 15 days following the completion of each' inservice inspection of steam generator tubes, the number of tubes plugged or repaired in l1 l 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 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 inspected,

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

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3) Identification of tubes plugged or repaired.

c. Result: of steam generator tube inspections which fall into Category C-3 shall be reported in a Special Report to the Commission pursuant -1 to Specification 6.9.2 within 30 days and prior to resumption'of plant operation. This report shall provide a descr'iption of investi- .

gations conducted to determine cause of the tube degradation and'  !

corrective measures taken to prevent recurrence.

zur , 1 D BYRON - UNITS 1 & 2 3/4 ~4-17 AMENDMENT NO. 58

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11) F* Distance is the distance into the tubesheet from the secondary face of the tubesheet or the top of the last hardroll, whichever is further into the tubesheet, that has been determined to be 1.7 inches.

12) F* Tube is a Unit 1 SG tube that contains a defect below the F*

distance and contains sound expanded tubing within the F* distance.

Defects contained in an F* tube are not dependant on flaw geometry.

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d. The results of inspections of F* Tubes shall be reported to the Commission prior to the resumption of plant operation. - The report shall include:

1) Identification of F* Tubes, and -

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2) Location and size of the degradation.

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TABLE 4.4-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION Preservice Inspection Yes No. of Steam Generators per Unit Four

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First Inservice Inspection Two l

Second & Subsequent Inservice Inspections One ' ,

TABLE NOTATION

1. Tne inservice inspection may be limited to one steam generator _on a rotating schedule encompassing 3 N % of the tubes (where N is the number of steam generators in the plant) if the results of the first.

or previous inspections indicate _that all steam generators are performing .in a like manner. Note that under some circumstances, the operating conditions in one or more steam generators may be:found to be more severe than those in other steam generators. Under'such circumstances the sample sequence shall be modifiedfto inspect the most severe conditions. Each of the other two steam generators.not inspected during the first inservice inspections shall be. inspected during the second and third inspections. The fourth and subsequent inspections shall follow the instructions described above.

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BYRON - UNITS 1 & 2 3/4 4-18

TABLE 4.4-2 tn

% STEAM GENERATOR TUBE INSPECTION

-E c- 1ST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION 5

g Sample Sire Result Action Required Result Action Required Result Action Required A mininum of C-1 None N.A. N.A. N.A. N.A.

N S Tubes per g, g, C-2 Plug or repair C-1 None N.A. N.A.

defective tubes and e inspect additional C-2 Plug or repair C-1 None -l 2S tubes in this defective tubes ,

and inspect C-2 Plug or repair -l S. G' additional 4S defective tubes tubes in this S. G.

C-3 Perform act. ion for C-3 result of first sample w C-3 Perform action for N.A. N.A.

1 C-3 result of first p sample

• C-3 Inspect all tubes in All other None N.A. N.A.

this S. G., plug or- S. G.s are repair defective C-1 tubes and inspect 2S tubes in each Some S. G.s Perform action for N.A. N.A.

Other S. G. C-2 but no C-2 result of additional second sample Notification to NRC S. G. are C-3 pursuant t Additional Inspect all tubes - N.A N.A.

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S. G. is C-3 in each S. G. and O

3 plug or repair M defective tubes. ~

5 Notification to .

M NRC pursuant to 4 550.72(b)(2) of g 10 CFR Part 50

$ here is 'the number nf steam generators in the unit, arid n is;the number nf steam 3 ,. 3 0% -oeneratnrs inspect.ed during an inspection n

, REACTOR COOLANT SYSTEM

. BASES 3/4.4.5 STEAM GENERATORS The Surveillance Requirements for inspection of the steam generator tubes  !

ensure that the structural integrity of this portion of the RCS will be main-  !

tained. The program for inservice inspection of steam generator tubes is i based on a modification of Regulatory Guide 1.83 Revision 1. Inservice inspectionofsteamgeneratortubingisessentialinordertomaintainsurveil- l lance of the conditions of the tubes in the event that.there is evidence of l mechanical damage or progressive degradation due to design, 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 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

, plant operation would be limited by the limitation of steam generator tube eb leakag{or etween the Reactor Coolant System and the Secondary Coolant System (reac to-secondary leakage - 500 gallons per day per steam generator .

Cracks operation willhaving have an a reactor-to-secondary adequate leakage margin of safety to withstand less than this the loads j 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 by radiation monitors of steam generator blowdown. Leakage in excess of this limit will require plant shutdown and an unscheduled inspectiun, during which the leaking tubes will be located and plugged or repaired by sleeving. The technical bases for sleeving are described in Westinohouse report WCAP-13698 Rev. I and Babcock & Wilcox Topical Report BAW-2045PA Rev. 1.

Wastage-type defects are unlikely with proper chemistry treatment of the secondary coolant. However even if a defect should develop in service, it willbefoundduringscheduledinservicesteamgeneratortubeexaminations.

Plugaing or sleeving will be required for all tubes with imperfections exceeding the plugging or repair limit of 40% of the tube nominal wall g".3 the Inickness,+ If a sleeved tube is found to contain a through wall penetration in Y sleeve of equal to or greater than 40% of the nominal wall thickness, the

.N/ /* b M/ tube must be plugged. The 40% plugging limit for the sleeve is derived from Reg. Guide 1.121 analysis and utilizes a 20% allowance for eddy current Mj g' uncertainty and additional degradation growth. Inservice inspection of sleeves is required to ensure RCS integrity. Sleeve ins U f # f. described in Westinghouse Report WCAP-13698 I andRev.pection techniques Babcock & Wilcox Topical are Report BAW-2045PA Rev. 1. Steam Generator tube and sleeve inspections have pe g" 1 demonstrated the capability to reliably detect degradation that has penetrated 20% of the pressure retaining portions of the tube or sleeve waH thickness.

Commonwealth Edison will validate the adequacy of any system that is used for periodic inservice inspection of the sleeves and, as deemed appropriate, will upgrade testing methods as better methods are developed and validated for commercial use.

f Whenever the results of any steam generator tubing inservice inspection

.QEET' fall into Category C-3, these results will be reported to the Commission )ur-

- suant to Specification 6.9.2 3rior to resumption of plant operation. Suci 2: cases will be considered by t1e 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 i Specifications, if necessary. 1 1

BYRON - UNITS 1 & 2 B 3/4 4-3 AMENDMENT _ NO. 58 ;

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- Pluggirig or repair is not required for tubes with;any_ type of '

degradation within' the tubesheet area and below the F*. distance with '

no degradation within the F* distance ~ The F* Criteria is based on:

Babcock &.Wilcox Nuclear Technologies (BWNT) Topical' Report BAW-10196 P, Revision 1.

F* tubes meet the structural integrity requirements with. appropriate: -

margins.for-safety as.specified in Regulatory. Guide:1.121 and the ~

ASME Boiler and Press'ure Vessel Code,'Section Ill, Subsection NB_.

and. Division I Appendices, for normal operating and faulted conditions. '

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ATTACHMENT 2b PROPOSED CHANGES TO APPENDIX A; TECHNICAL SPECIFICATIONS FOR FACILITY.

OPERATING LICENSES NPF-72 and NPF-77--

BRAIDWOOD P

l Revised Pages: 3/4 4 -13* ,

3/4 4 -14 -

3/4 4-14a*

3/4 4 -15*'

3/4 4 -16 3/4 4 -17*

. - 3/4'4 -17a' i --

3/4 4 -17b - #

3/4'4 -18*-

3/4 4 -19*

B 3/44-3 Pages indicated with an asterisk (*) are not being revised and are only included for convenience.

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REACTOR COOL ANT SYSTf2 3/4.4.5 STEAM GENERATORS LIMITING CONDITION FOR OPERATION g .

3.4.5 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 steam generator (s) to OPERABLE status prior to increasing T, above 200*F.

SURVEILLANCE RE0VIREMENTS 4.4.5.0 Each steam generator shall be demonstrated OPERABLE by perfonnance of the following augmented inservice inspection program and the requirements of.

Specification 4.0.5.

4.4.5.5 luq Q.gapater Samole Selection and InspectiED - Each steam generator -

snall 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

• Samole Selection and Insnection - The steam . J

_ (- 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 fre--

quencies. 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. When applying the expectations of 4.4.5.2.a through 4.4.5.2.c, previous defects. or imperfections in the area repaired by the sleeve are not considered 'an area requiring reinspection. The tubes selected for each inservice inspection shall-include at least 3% 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;

b. The first sample of tubes selected for each inservice. inspection.

-(subsequent to the preservice inspection) of each steam generator _.

shall include: '

b ,

• 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;4.5.4.a.10. -

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30M COOD = UNITS ] 1? 3/4 4-13 A"EN?"ENT N015:

REACTOR COOLANT SYSTEM SURVEILLANCE RE0VIREMENTS (Continued)

All tubes that previously had detectable tube wall penetrations

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1) greater than 20% that have not been plugged or sleeved in the affected area, and all tubes that previously had detectable ' sleeve wall penetrations that have not been plugged,

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

3) At least 3% of the total number of sleeved tubes in all four steam generators or all of the sleeved tubes in the generator chosen for the inspection program, whichsver is less. These inspections will incit Je both the tube and the sleeve, and- -l

4) A tube inspection (pursuant to Specification 4.4.5.4a.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 inspection, this shall be recorded and an adjacent tube shall be selected and gg subjected to a tube inspection j aul M 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, and

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

d. For Unit I Cycle 3, implementation of the tube support plate interim t plugging criteria limit requires a 100% bobbin coil probe inspection for (

all hot leg tube support plate intersections and all cold leg (

intersections down to the lowest cold leg tube support plate with outer ,

diameter stress corrosion cracking (ODSCC) indications. An inspection (

using a rotating pancake coil (RPC) probe is required in order to show ,

OPERABILITY of tubes with flaw-like bobbin coil signal amplitudes greater  :

than 1.0 volt but less than or equal to 2.7 volts. For tubes that will be (

administratively plugged or repaired, no RPC inspection is required. The 4 RPC results are to be evaluated to establish tW the principal indications can be characterized as ODSCC. (

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

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

BRAIDWOOD~- UNITS 1 & 2 3/4 4-14 " NIT 1 - AMENDuENT NO

. . , .n .. . . . -  !. - * * - =* = ~- = *

- ATTACHMENT 6 .i Babcock & Wilcox Nuclear Technologies W-D4'F* QUALIFICATION REPORT.

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BAW-10196 NON-PROPRIETARY >

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155 M a Tbdga n aus B&WNUCLEAR TECHNOLOGIES ,

Special Products & Integrated Services El

! Teiecopy atM-n32mn l

! I Ahril 4,1994 SGBM-94-3299 i

Mr. J.R. Smith Commonwealth Edison Company i Byron Nuclear Station 4450 N. Gennan Church Road .

Bymn, IL 61010 ,

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Subject:

F+ Non-Proprietary Infonnation;

Dear Jay:

This letter provides BWNT concurrence for CQmmonwealth Edison Co. to utilize the 1.7 inch F*

length, as delineated in BWNT topical reports lBAW-10196P-01 arx1 BAW-10197P-01, as non-pmprietary information in preparing technical specification change docmnentation for NRC review 1 as well as any similar associated documentation. In addition, Figure 1.1 of BWNT non-proprietary topical repon BAW-10196-00 is in fact non-proprietary and therefore can be treated as such regardless of the header which indicates the contrary.

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Very truly y ,

M, nd R) <

F.J; evandoski-

Senior Product Manager slo

fjl-4213 ,

cc: D.E. St. Clair i G.D. Comrady  ;

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