View source for LIC-05-0137, Revised License Amendment Request, Deletion of Sleeving as a Steam Generator Tube Repair Method

{{Adams
| number = ML053550202
| issue date = 12/19/2005
| title = Revised License Amendment Request, Deletion of Sleeving as a Steam Generator Tube Repair Method
| author name = Ridenoure R
| author affiliation = Omaha Public Power District
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000285
| license number = DPR-040
| contact person = 
| case reference number = LIC-05-0137
| document type = Letter type:LIC, License-Application for Facility Operating License (Amend/Renewal) DKT 50, Technical Specification, Bases Change
| page count = 30
| project = 
| stage = Request
}}

=Text=
{{#Wiki_filter:upp"i Omaha Public Power District 444 South 16th Street Mall Omaha NE 68102-2247 Employment with Equal Opportunity December 19,2005 LIC-05-0137 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

==References:==
: 1. Docket No. 50-285
: 2.      Letter from OPPD (R. T. Ridenoure) to NRC (Document Control Desk) dated November 7, 2005, "Fort Calhoun Station Unit No. 1 License Amendment Request, "Deletion of Sleeving as a Steam Generator Tube Repair Method,""(LIC-05-0121)

==SUBJECT:==
Fort Calhoun Station Unit No. 1 Revised License Amendment Request, "Deletion of Sleeving as a Steam Generator Tube Repair Method" In the Reference 2 License Amendment Request, Omaha Public Power District (OPPD) proposed to change the Fort Calhoun Station Technical Specifications by deleting the sleeving repair alternative to plugging for steam generator tubes. OPPD has subsequently determined that the scope of this request must include increasing the number of tubes required for steam generator tube surveillances to be consistent with the increased number of tubes in the replacement steam generators. Therefore, this revised License Amendment Request supersedes the Reference 2 request.
Pursuant to 10 CFR 50.90, OPPD hereby proposes to change the Fort Calhoun Station (FCS)
Technical Specifications by deleting the sleeving repair alternative to plugging for steam generator tubes. OPPD also proposes to increase the steam generator tube sample sizes for surveillances. The FCS replacement steam generators (RSGs) to be installed during the fall of 2006 are manufactured by Mitsubishi Heavy Industries, Ltd. (MHI). These changes are being requested because OPPD has determined that the sleeving repair alternative to plugging will not be used for the MHI RSGs, and because the RSGs have an increased number of tubes.
HighostloCustomer SatisfacRioit With Reskidetial Electric Service Among Medium-SIzed Utilities For the fifth year in a row, Omaha Public Power District has received a J.D. Power and Associates award for Highest Customer Satisfaction With Residential Electric Service.
J.D. Power and Associates 2001- 2005 Electric Utility Residential Customer Satisfaction Studies?. 2005 study based on a total of 26,782 consumer responses. The top 23 medium electric companies were ranked in the study. wwwldpowercom.                                       6 ,

U. S. Nuclear Regulatory Commission LIC-05-0137 Page 2 The proposed Technical Specification change has been evaluated in accordance with 10 CFR 50.91(a)(1) using criteria in 10 CFR 50.92(c); it has been determined that this change involves no significant hazards considerations.        The bases for these determinations, information supporting the change, a no significant hazards consideration, and an environmental consideration are included in the attached submittal. provides the No Significant Hazards Consideration and the Applicable Regulatory Requirement/Criteria for this requested change to the Technical Specifications. Attachment 2 contains the marked-up pages and Attachment 3 contains the clean version reflecting the requested Technical Specification and Basis changes.
OPPD requests approval of the proposed amendment by October 1, 2006, to support implementation during the 2006 refueling outage. OPPD requests that the effective date for this Technical Specification change be no later than the end of the 2006 refueling outage to allow for implementation of these proposed changes. No new commitments are made to the NRC in this letter.
In accordance with 10 CFR 50.91, a copy of this application is being submitted to the designated Nebraska State Official.
I declare under penalty of perjury that the foregoing is true and correct. (Executed on December 19, 2005)
If you have any questions or require additional information, please contact Mr. T. C. Matthews at (402) 533-6938.
Sincerely,            -
R.T. Ri fenou ice Pr sident Omaha ublic Power District RTR/RLJ/rlj Attachments:
: 1. Omaha Public Power District's Evaluation
: 2. Markup of Technical Specification Pages
: 3. Proposed Technical Specifications (clean) c:       Division Administrator - Public Health Assurance, State of Nebraska

LIC-05-0137 Page 1 ATTACHMENT 1 Omaha Public Power District's Evaluation For Amendment of Operating License Deletion of Sleeving as a Steam Generator Tube Repair Method and Revision of Minimum Sample Sizes

==1.0    DESCRIPTION==
 ......................................                  2

==2.0    PROPOSED CHANGE==
 .......................................             2

==3.0    BACKGROUND==
 .......................................                  2

==4.0    TECHNICAL ANALYSIS==
 .......................................          2

==5.0   REGULATORY ANALYSIS==
 .......................................          3 5.1   No Significant Hazards Consideration (NSHC) 5.2   Applicable Regulatory Requirements/Criteria

==6.0    ENVIRONMENTAL CONSIDERATION==
 ...................................... 5

==7.0    REFERENCES==
 ......................................                  5

LIC-05-0137 Attachment 1 Page 2 Omaha Public Power District's Evaluation for Amendment of Operating License

==1.0   DESCRIPTION==

This letter is a request to amend Operating License DPR-40 for Fort Calhoun Station, Unit No. 1 (FCS). The proposed changes delete steam generator tube sleeving as an alternative to plugging for steam generator tube repairs. The proposed changes also increase the number of tubes required for steam generator tube surveillances to be consistent with the increased number of tubes in the replacement steam generators.

==2.0   PROPOSED CHANGE==

Omaha Public Power District (OPPD) proposes to change Technical Specification (TS) 3.17, Steam GeneratorTubes, and its Basis by removal of all text and requirements related to the leak tight tube sleeves. Corresponding changes are proposed for Table 3-13, Steam GeneratorTube Inspection. Deletion of Table 3-14, Steam Generator Tube Sleeve Inspection, is proposed.
Finally, OPPD proposes to increase the 1" inspection sample size from 300 tubes per original SG to 312 tubes per replacement SG. OPPD also proposes to increase the 1st and 2 nd Sample Inspection "Action Required" sample sizes from 600 and 1200 tubes per original SG to 624 and 1248 tubes per replacement SG, respectively.

==3.0    BACKGROUND==

The sleeving repair method for Combustion Engineering steam generators was added to the FCS Technical Specifications by Amendment 195 (Reference 7.1). During the 2006 Refueling Outage, replacement steam generators (RSGs) will be installed at FCS. Because the RSGs are manufactured by Mitsubishi Heavy Industries, Ltd. (MHI), the RSG tubes do not have an approved sleeving repair alternative to plugging. Therefore, OPPD is requesting the deletion of the sleeving capability from the Technical Specifications because analyses supporting the existing specification are not applicable to the MHI steam generators.
Each RSG contains 5,200 tubes, 195 tubes more than the 5,005 tubes contained in each original steam generator. The inspection and action program in Table 3-13, Steam Generator Tube Inspection, is based on 3% of the total number of tubes in each steam generator consistent with Regulatory Guide 1.83, Revision 1, as referenced in Technical Specification 3.17(2). Therefore, the "Sample Size" and the additional "Action Required" sample size of the 1 st and 2 nd Sample Inspections in Table 3-13 must be increased to be consistent with the increased number of tubes in the RSGs.

==4.0    TECHNICAL ANALYSIS==

The proposed changes remove text in the Technical Specifications related to the surveillance requirements of leak tight sleeves, and the reference to the EPRI PWR Steam Generator

LIC-05-0137 Attachment I Page 3 Examination Guidelines in the basis. Other TS changes, not related to tube sleeving, made during the process of approving Amendment 195 are not being affected or altered.
The proposed changes remove the capability for the repair of degraded steam generator tubes using sleeving which was approved for the original Combustion Engineering steam generators.
These generators are being replaced in the fall of 2006 with steam generators manufactured by Mitsubishi Heavy Industries, Ltd. (MHI) which are not expected to use the tube sleeving alternative to tube plugging. The proposed changes eliminate tube sleeving as a repair for the replacement steam generator tubes. These changes are necessary, not as a result of new or enhanced analyses or evaluations, but as a consequence of MHI's steam generator operating experience which has not resulted in the need to develop the sleeving repair option.
The RSGs contain 5,200 tubes per steam generator, 195 tubes more than the 5,005 tubes in each original steam generator. The proposed increases in the "Sample Size" and "Action Required" sample sizes of the I" and 2nd Sample Inspections prescribed in Table 3-13, Steam Generator Tube Inspection, maintains an inspection and action program of 3% of the total number of tubes to be consistent with the increased number of tubes in the replacement steam generators. The installation of the RSGs with 5,200 tubes per steam generator has been assessed under the 50.59 criteria and determined to not require NRC review.
The proposed changes do not alter, degrade, or prevent actions described or assumed in any accident analysis. They will not change any assumptions previously made in evaluating radiological consequences or affect any fission product barriers, nor do they increase any challenges to safety systems. Therefore, the proposed changes do not increase or have any impact on the consequences of events described and evaluated in Chapter 14 of the Fort Calhoun Updated Safety Analysis Report (USAR).

==5.0 REGULATORY ANALYSIS==

5.1. No Significant Hazards Consideration Omaha Public Power District has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:
: 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The elimination from the Technical Specifications surveillance requirements of leak tight sleeves as a repair method alternative to plugging defective steam generator tubes does not introduce an initiator to any previously evaluated accident. The frequency or periodicity of performance of the remaining surveillance requirements for steam generator tubes (including plugged tubes) is not affected by this change. Elimination of the tube repair method has no effect

LIC-05-01 37 Attachment I Page 4 on the consequences of any previously evaluated accident. The proposed changes will not prevent safety systems from performing their accident mitigation function as assumed in the safety analysis. Increasing the number of tubes in required surveillance samples maintains the assumed sample size percentage of the total tubes and the proportional scope of additional inspections.
Therefore, this change does not involve a significant increase in the probability or consequences of any accident previously evaluated.
: 2.       Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed change only affects the Technical Specifications surveillance requirements. The proposed change is a result of installation of replacement steam generators. The proposed change will eliminate a steam generator tube repair alternative which cannot be utilized or credited for the replacement steam generators. This change will not alter assumptions made in the safety analysis and licensing bases. Increasing the number of tubes in required surveillance samples maintains the assumed sample size percentage of the total tubes and the proportional scope of additional inspections.
Therefore, this change does not create the possibility of a new or different kind of accident from any previously evaluated.
: 3.      Does the proposed change involve a significant reduction in a margin of safety?
Response: No.
The proposed change deletes surveillance requirements for a steam generator tube repair alternative which will no longer be necessary or applicable. Increasing the number of tubes in required surveillance samples maintains the assumed sample size percentage of the total tubes and the proportional scope of additional inspections. Therefore, the remaining Technical Specification steam generator tube surveillance requirements, including inspection and plugging requirements, will continue to maintain the applicable margin of safety.
Therefore, this Technical Specification change does not involve a significant reduction in the margin of safety.
Based on the above, Omaha Public Power District concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.

LIC-05-0 137 Attachment 1 Page 5 5.2 Applicable Regulatory Requirements/Criteria The proposed Technical Specifications changes are deleting surveillance requirements for a steam generator tube repair alternative (sleeving) which will no longer be utilized or credited. Likewise, the analyses supporting the tube sleeving repair alternative are not applicable and are not planned to be applied to the replacement steam generators. Thus, the proposed changes eliminate requirements not applicable for the replacement steam generators. The Technical Specifications will still contain the steam generator tube surveillance requirements consistent with Regulatory Guide 1.83, Revision 1, updated to reflect the increase in the number of SG tubes in the replacement SGs, which existed before tube sleeving was incorporated by Amendment 195 (Reference 7.1). Other TS changes, not related to tube sleeving, made by Amendment 195 are not being affected or altered. In accordance with the FCS general design criteria (Reference 7.2), the FCS Technical Specifications are being revised as a result of a change in facility equipment.
In conclusion, based on the considerations discussed above, (I) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

==6.0 ENVIRONMENTAL CONSIDERATION==

Based on the above considerations, the proposed amendment does not involve and will not result in a condition which significantly alters the impact of Fort Calhoun Station on the environment.
Thus, the proposed changes meet the eligibility criteria for categorical exclusion set forth in 10 CFR Part 51.22(c)(9), and, pursuant to 10 CFR Part 51.22(b), no environmental assessment need be prepared.

==7.0 REFERENCES==

7.1. Letter from NRC (L. R. Wharton) to OPPD (S. K. Gambhir) dated March 1, 2001, Issuance of Amendment Re: Leak Tight Sleeves as an Alternative Tube Repair Method To Plugging Defective Steam Generator Tubes (TAC No. MA9653) (NRC-01-012) 7.2. Fort Calhoun Station Updated Safety Analysis Report, Responses to 70 Criteria, Appendix G.

LIC-05-0137 Page 1 ATTACHMENT 2 Mark-up of Technical Specification Pages

TECHNICAL SPECIFICATIONS TECHNICAL SPECIFICATIONS - TABLES TABLE OF CONTENTS TABLE
_ As _ __ __                                                             A_ as-__ ^ A7 Uenerator Tue Sleeve inspection .................................
L 3 1i4   Steam                                                                                         Section3.1    I 5.2-1   Minimum Shift Crew Composition ..........................                                       Section 5.0 TOC - Page 5            Amendment No.I 16,125,142,1415,152,176,495

TECHNICAL SPECIFICATIONS TECHNICAL SPECIFICATIONS                   - TABLES TABLE OF CONTENTS (ALPHABETICAL ORDER)
Continued TABLE             DESCRIPTION                                                                                                 SECTION 2-10    Post-Accident Monitoring Instrumentation Operating Limits ............................................              Section 2.21 2-9     RCS Pressure Isolation Valves ............................................                                           Section 2.1 3-6     Reactor Coolant Pump Surveillance ...............................................                                    Section 3.3 1-1     RPS LSSS ...............................................                                                             Section 1.0 3-13    Steam Generator Tube Inspection ..............................................                                      Section 3.17 3 11    Steam Gnerator Tubo Slleve Inspection...............................................................................Section 3.17 2-11    Toxic Gas Monitoring Operating Limits ............................................                                  Section 2.22 TOC - Page 7                Amendment No. 116,145,152,176,495

TECHNICAL SPECIFICATIONS 3.0   SURVEILLANCE REQUIREMENTS 3.17  Steam Generator Tubes Applicability Applies to in-service surveillance of steam generator tubes.
Obiective To ensure the integrity of the steam generator tubes.
Specifications Each steam generator shall be demonstrated OPERABLE by performance of the following in-service inspection program.
(1)     Steam Generator Sample Selection and Inspection Methods The in-service inspection shall be performed on each steam generator on a rotating schedule. Under some circumstances, the operating conditions in one steam generator may be found to be more severe than those in the second steam generator. Under such circumstance, the sample sequence shall be modified to inspect the steam generator with the most severe conditions.
(2)    Steam Generator Tube Sample Selection and Inspection The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 3-13. The in-service inspection of steam generator tubes shall be performed according to Specification 3.17(4)(i), "Tube Inspection," and at the frequencies specified in Specification 3.17(3).
The inspected tubes shall be verified acceptable per the acceptance criteria of Specification 3.17(4). When applying the exceptions of (i), (ii) and (iii) below, previous degradiati      imprf      nc Or dofc=nt4ri tho arpA of tho tubA repaired by slieving are neo considered an area requiring rcinspection or inspcction of adjacent tubes. The tubes selected for each in-service inspection shall include at least 3% of the total tubes in the steam generators and the tubes selected for these inspections shall be selected on a random basis, except:
(i)    If the tube is recorded as a degraded tube, then an adjacent tube shall be inspected.
(ii)    The first sample inspection during each in-service inspection of each steam generator shall include all non-plugged tubes that previously had detectable wall penetrations (>20%) and shall also include tubes in those areas where experience has indicated potential problems.
(iii)   The second and third sample inspections, if required, may be less than an entire tube length inspection provided the inspection concentrates on those areas of the tube 3.17 - Page 1                       Amendment No. 104,195

TECHNICAL SPECIFICATIONS 3.0  SURVEILLANCE REQUIREMENTS 3.17  Steam Generator Tubes (Continued) sheet array and on those portions of the tubes where defects were previously detected.
(iv)     To the extent practical, 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 results of each sample inspection shall be classified into one of the following three categories (this classification shall apply to the inspection of tubes and is exclusive of the slceve inspection requirements in Specification 3.17(2a)).
Category                                        Inspection Results C-1                             No more than 5% of the tubes inspected are degraded and none of the inspected tubes are defective.
C-2                             No more than 1%of the tubes inspected are defective, or between 5%and 10% of the tubes inspected are degraded.
C-3                              More than 1%of the tubes inspected are defective, or more than 10% of the tubes inspected are degraded.
NOTE: In all inspections, previously degraded tubes must exhibit growth of greater than 10% through wall or growth of greater than 25% of the repair limit to be included in the above calculations.
(2a)   Steam GenFratFr      Tube Sleeve Sample-Selecion and I nspectin The steam generator tube sleeve minimum sample size, inpection rellification and the corresponding action required shall be as specified in Table 3 11. The in-servie inspection of steam generator tube sleeves shall be performed according to Specification 3.17(1)(i), "Tube Sleevc Inspection," and at the freeuoncios specified in Specification 3.17(3). The inspected tube sleeves shall be verified acceptable per the acceptance criteria of Specifiation 3.17(4). The tube sleeves selected for each in serzice inection shall include at least 20% of the total number of tube sleeves in the steam generators and the tube sleeves selected for these inspections shall be selected on a random basis, exreept:
(i)      If the tube sleeve is recorded as a degraded tube sleeve and an adjacent tube sleeve exists, then an adjacent tube sleeve shall be inspected.
(ii)     The first sample inSPectioRduring each in service inspection of each steam generator shall include all tube sleeves in non plugged tubes that previously had detectable wall penetrations (>20%) and shall also include tube sleeves in those areas where       ri       has iRdicated potential problems.
3.17 - Page 2                     Amendment No. 104, 195

TECHNICAL SPECIFICATIONS 3.0  SURVEILLANCE REQUIREMENTS 3.17  Steam Generator Tubes (Continued) 0ii)     To the extent practical, where experience in similar plants with similar water chemistry indicates critical areas to be inspccted, then at least 50% of the tube sleeves inspected shall be from these critical areas. Where the number of sleeves
                                                                                          ., _, _, -__. ._ - _ .~ -_
in the critical areas represe nt less than 50% of the initial sampIce   all si          in the 1cs Gritical areas shall be inspe The results of each sample inspection shall be classified into one of the following three categories (this classification shall apply to the inspection of sleeves and is exclusive of the tube inspection requirements in Specification 3.17(2)).
Caiegory                           Inspection Results C1                         No more than 5%of the tube sleeves inspected are degraded and none of the inspected tube sleeves are defective.
C2                         No more than 1% of the tube sleeves inspected are defective, or between 5%and 10% of the tube sleeves inspected are degraded.
C3                         More than 1%of the tube sleeves inspected are defective, or more than 10% of the tube sleeves inspected are degraded.
NOTE: In all inspections, previously degraded tube sleeves must exhibit growth of greater than 10%through wall or growth of greater than 25% of the repair limit to be included in the ;above rcalculationR.
(3)    Inspection Frequencies The above required in-service inspections of steam generator tubes and tube sleeves shall be performed at the following frequencies (inspections shall be performed, unless otherwise specified, coincident with refueling outages or any scheduled cold shutdown for plant repair and maintenance):
(i)     In-service inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection, subject to the following clarifications and exceptions.
: 1.        If a plant operating cycle is less than 12 months, inspections may be performed at the end of that cycle.
: 2.        If two consecutive tube inspections following service under all volatile treatment conditions result in all inspection results falling into the C-1 category or if two consecutive tube inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the tube inspection interval may be extended to a maximum of once per 40 months.
3.17 - Page 3                      Amendment No. 4-04,495

TECHNICAL SPECIFICATIONS 3.0  SURVEILLANCE REQUIREMENTS 3.17 Steam Generator Tubes (Continued)
: 3.      Thne inspections of tube sleeves snail be configured to ensure mat each individual tube sleeve is inspected at least oncc in 60 months, with the following excreptien: if the 60 month time frame falls during an operating cycle, comprletion of that cycle is acceptable prier to meeting this (ii)   Increased Inspection Frequencies
: 1.      If results of the in-service inspection of the steam generator tubes conducted in accordance with Table 3-13 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 a subsequent inspection meets the conditions specified in Section 3.17(3)(i)2 above, at which time the interval can be extended to a 40-month period.
: 2.       If results of the inscr icc inspection of tube sleeves conducted in rte      v... 4. 'r-tl Tel  - 4 A fell-& ;4- fnr:      r  -     -f - -h -_rA~~
                                                                                                     -    reon ._.
shall be increased such that 100% of the tube sleeves in the affected steam generator arc inspected during subsequent inspections. The increase in inspection frequency shall apply until two consecutive tube sleeve inspections meet the conditions for Category C 1 or two consecutive tube sleeve inspections demonstrate that previously observed degradation has nRt continued and no ationl                 degradatien has occrsred, at which time the iRspection frequency of SpecificatinR 3.47(3)(i)3 shall again apply.
(iii) Unscheduled in-service inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Tables 3-13 aid 3 44 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 Section 2.1.4 of the Technical Specifications,
: 2.      A seismic occurrence greater than the Operating Basis Earthquake,
: 3.      A loss-of-coolant accident requiring actuation of the engineered safeguards, or
: 4.      A main steam line or main feedwater line break.
3.17 - Page 4                          Amendment No. 404,495

TECHNICAL SPECIFICATIONS 3.0  SURVEILLANCE REQUIREMENTS 3.17 Steam Generator Tubes (Continued)
(4)   Acceptance Criteria (i)    As used in this specification:
Imperfection means an exception to the dimensions, finish or contour of a tube er sleeve-from that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal tube er sleeve wall thickness, if detectable, may be considered as imperfections.
Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube or sleeve.
Degraded Tube-er-Sleeve means a tube er sleeve containing imperfections >20%
of the nominal wall thickness caused by degradation. Any tube which does not permit the passage of the eddy-current inspection probe through its entire length and U-bend shall be deemed a degraded tube. Any tube sleeve which does not permit the passage of the eddy current inspection probe through its entire length shall be deemed a degraded sleeve.
                 % Degradation means the percentage of the tube er sleeve wall thickness affected or removed by degradation.
Defect means an imperfection of such severity that it exceeds the plugging eF repair limit.
Plugging er-Repair Limit means the imperfection depth at or beyond which the tube shall be removed from service by plugging or repaired by sleeving in the affeeted area-because it may become unserviceable prior to the next inspection.
Plugging er-repair limit is equal to 40% of the nominal tube wall thickness for the original tube wall. Sleeved tubes shall be plugged upon detection of unacc9ptablo degradiation in the pressure boundary region of the sleeve.
Unserviceable describes the condition of a tube er sleeve if it leaks in excess of analyzed limits or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break.
Tube or Tubing means that portion of the tube which forms the primary system to the secondary system pressure boundary.
Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg, excluding any areas defined under "Tube Sleeve lnspection".
3.17 - Page 5                     Amendment No. 1404,495

TECHNICAL SPECIFICATIONS 3.0  SURVEILLANCE REQUIREMENTS 3.17 Steam Generator Tubes (Continued)
Tube Repair or Sleeve refers to a process that re establishes tube sericeability.
Acceptable tube repairs will be pe~orfned usnRg the Combustion Engineering, InR.
Leak Tight Sleeve as described in the proprietary Combustion Engineering, Inc.
Report, CEN 630 P, Revision 02, "Repair of 3/A," O.D. Steam Generator Tubes Using Leak Tight Sleeves," june 1997.
Tube repair includes the removal of plugs that were previously installed as a corrective or prreventiveesur asfor e      the puFpose of sleeVing the tube. A tube inspection as defined herein is required prior to returning previously plugged tubes to service.
Tube Sleeve inspestion refers to inspection of the section of the steam generator tube repaired by sleeving. This includes the pressure retaining portions of the parent tube in contact with the sleeve, the sleeve to tube weld, and the pressure retaining portion of the sleeve.
(ii)   The steam generator shall be determined OPERABLE after completing the corresponding actions (plug eorrepair all tubes exceeding the plugging or repair limit and all tubes containing through-wall cracks, plug all tubes with sleeves containing defects) required by Tables 3-13 and 3 14.
(5)   Reporting Requirements (i)    Following each in-service inspection of steam generator tubes, the number of tubes plugged eo repaired in each steam generator shall be reported to the Commission within 30 days.
(ii)   The complete results of the steam generator tube in-service inspection shall be reported to the Commission within 6 months following completion of the inspection.
This report shall include:
: 1.      Number and extent of tubes and tube sleeves inspected.
: 2.      Location and percent of wall thickness penetration for each imperfection.
: 3.      Identification of tubes plugged.
: 4.      Identification of tubes repaired by rleeving.
3.17 - Page 6                     Amendment No. 104,195

TECHNICAL SPECIFICATIONS 3.0  SURVEILLANCE REQUIREMENTS 3.17 Steam Generator Tubes (Continued)
(iii) Results of steam generator tube inspections which fall into Category C-3 and require prompt notification of the Commission shall be reported prior to resumption of plant operation. The written followup of this report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
3.17 - Page 7                      Amendment No. 495, 228

TECHNICAL SPECIFICATIONS TABLE 3-13 STEAM GENERATOR TUBE INSPECTION 1st Sample Inspection                                  2nd Sample Inspection                 3rd Sample Inspection Sample Size         Result       Action Required       Result        Action Required          Result        Action Required A minimum of           C-1               None              N/A                 N/A               N/A                   N/A per S.G.               C-2   Plug oFrepair defective       C-1                None               N/A                   N/A ptubes and inspect additional 600 624 tubes      C-2     Plug eIF-FepaiF defective     C-I                 None in this S.G.                          tubes and inspectC2                    PlgP-eadfctv additional 1200 1248          C-2      Plug orepair defective tubes in this S.G.                     tubes C-3     Perform action for C-3        C-3      Perform action for C-3 result of first sample                 result of first sample C-3   Inspect all tubes in this The                    None               N/A                   N/A S.G., plug oF repair      second defective tubes and       S.G. is inspect 600 624 tubes in  C-1 other S.G.
The         Perform action for C-2        N/A                   N/A Prompt notification to    second      result of second NRC pursuant to           S.G. is     sample specification 5.6         C-2 The         Inspect all tubes in the      N/A                  N/A second      second S.G. and plug S.G. is     eo repair defective C-3         tubes. Prompt notification to NRC pursuant to specification 5.6 N/A~~No apial3.-Pae8Aed                                                                       ntN.               .-
                                                                                                                              .69A-4 N/A Not applicable                                      3.17 - Page 8                                 Amendment No. 46,99,1041, 195

TECHNICAL SPECIFICATIONS TABLE 3-14 STEAM GENERATOR TUBE SLEEVE INSPECTION 1st Sample Inspection                                                         2nd Sample Inspection Samplo Size            Result                 Action Required               Result                Action Required A minimum of         of'%
the -    A                         None                 -N/A                             N/A installed tube sleeves
                             - b-2         Plug tubes containing defective                                       None sleeves and inspect all remaining installed sleeves in this S.G.              G4        Plug tubes containing defective see:es
                                                                                       - 3       Perform action for C 3 result ot fiFst sample C3        Inspect all installed sleeves in-this The seGod                       None S.G., plug tubes containing           S.G. s defective sleeves, and inspect a minimum of 20% of the installed       The seGend      Perform action for C 2 result of sleeves in other S.G.                 S.G. is C 2     firs-t sample Add the tubes with defective          The secend      Inspect all sleeves in the second sledvstotenumber wf        defective  S.G. isC 3      S.G. and plug tubes ontanRing
___eelisto   the_ numberofdefective_                  defective sleeves. Add the tubes tubes list for NRC notification per                   with defcctive sleeves to the able3-13                                            number of defective tubes list for
_  NRC notification per Table 3 13 N/- - Not   DnlicabIA                                      317    P   'le9                                       Amendeint hli    1fi5

3.0   SURVEILLANCE REQUIREMENTS 3.17  Steam Generator Tubes (Continued)
Basis The surveillance requirements for inspection of the steam generator tubes and tube sleeves ensure that the structural integrity of this portion of the RCS will be maintained.
The program for in-service inspection of the steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1, dated July 1975. The programGfor in service inspection of steoam genrerator tube sleeves is based on a modification of EPRI PWR Steam Generator Examination Guidelince, Revision 5, Dated SCptembcr 1997.
In-service inspection of steam generator tubing and tube sleeves is essential in order to maintain surveillance of the conditions of the tubes and sleeves-in the event that there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or in-service conditions that lead to corrosion.
In-service inspection of steam generator tubing and tube sleeves also provides a means of characterizing the nature and cause of any tube er-sleeve-degradation so that corrective measures can be taken.
Tubes with defects may be repaired by a Combustion Engineering, !nc. Leak Tight Sleeve. The technical bases for sleeving repair are described in the Proprietary Combustion Engineering, Inc. Report CEN 630 P, Revision 02, "Repair of 3/14" O.D.
Steam Generator Tubes Using Leak Tight Sleeves," June 1997.
Whenever the results of any steam generator tubing in-service inspection fall into Category C-3, these results will be promptly reported to the Commission prior to the 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.
3.17 - Page 10                  Amendment No. 104,195, 228

LIC-05-0137 Page 1 ATTACHMENT 3 Proposed Technical Specification Pages

TECHNICAL SPECIFICATIONS TECHNICAL SPECIFICATIONS - TABLES TABLE OF CONTENTS TABLE 5.2-1   Minimum Shift Crew Composition ..........................                                Section 5.0 TOC - Page5         Amendment No. 116,125,112,145,152,176,105

TECHNICAL SPECIFICATIONS TECHNICAL SPECIFICATIONS - TABLES TABLE OF CONTENTS (ALPHABETICAL ORDER)
Continued TABLE             DESCRIPTION                                                                     SECTION 2-10    Post-Accident Monitoring Instrumentation Operating Limits .Section                              2.21 2-9     RCS Pressure Isolation Valves .Section                                                           2.1 3-6     Reactor Coolant Pump Surveillance .                                                      Section 3.3 1-1     RPS LSSS .Section                                                                                1.0 3-13    Steam Generator Tube Inspection .                                                      Section 3.17 2-11    Toxic Gas Monitoring Operating Limits .                                                Section 2.22 TOC - Page 7               Amendment No. 116,1415,152,176,195

TECHNICAL SPECIFICATIONS 3.0   SURVEILLANCE REQUIREMENTS 3.17  Steam Generator Tubes Applicability Applies to in-service surveillance of steam generator tubes.
Objective To ensure the integrity of the steam generator tubes.
Specifications Each steam generator shall be demonstrated OPERABLE by performance of the following in-service inspection program.
(1)     Steam Generator Sample Selection and Inspection Methods The in-service inspection shall be performed on each steam generator on a rotating schedule. Under some circumstances, the operating conditions in one steam generator may be found to be more severe than those in the second steam generator. Under such circumstance, the sample sequence shall be modified to inspect the steam generator with the most severe conditions.
(2)    Steam Generator Tube Sample Selection and Inspection The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 3-13. The in-service inspection of steam generator tubes shall be performed according to Specification 3.17(4)(i), "Tube Inspection," and at the frequencies specified in Specification 3.17(3).
The inspected tubes shall be verified acceptable per the acceptance criteria of Specification 3.17(4). The tubes selected for each in-service inspection shall include at least 3% of the total tubes in the steam generators and the tubes selected for these inspections shall be selected on a random basis, except:
(i)    If the tube is recorded as a degraded tube, then an adjacent tube shall be inspected.
(ii)   The first sample inspection during each in-service inspection of each steam generator shall include all non-plugged tubes that previously had detectable wall penetrations (>20%) and shall also include tubes in those areas where experience has indicated potential problems.
(iii)   The second and third sample inspections, if required, may be less than an entire tube length inspection provided the inspection concentrates on those areas of the tube sheet array and on those portions of the tubes where defects were previously detected.
3.17 - Page 1                     Amendment No. 104,195,

TECHNICAL SPECIFICATIONS 3.0  SURVEILLANCE REQUIREMENTS 3.17 Steam Generator Tubes (Continued)
(iv)      To the extent practical, 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 results of each sample inspection shall be classified into one of the following three categories.
Category                                           Inspection Results C-1                                No more than 5% of the tubes inspected are degraded and none of the inspected tubes are defective.
C-2                                No more than 1% of the tubes inspected are defective, or between 5% and 10% of the tubes inspected are degraded.
C-3                                More than 1% of the tubes inspected are defective, or more than 10% of the tubes inspected are degraded.
NOTE: In all inspections, previously degraded tubes must exhibit growth of greater than 10% through wall or growth to be included in the above calculations.
(3)   Inspection Frequencies The above required in-service inspections of steam generator tubes shall be performed at the following frequencies (inspections shall be performed, unless otherwise specified, coincident with refueling outages or any scheduled cold shutdown for plant repair and maintenance):
(i)      In-service inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection, subject to the following clarifications and exceptions.
: 1.       If a plant operating cycle is less than 12 months, inspections may be performed at the end of that cycle.
: 2.       If two consecutive tube inspections following service under all volatile treatment conditions result in all inspection results falling into the C-1 category or if two consecutive tube inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the tube inspection interval may be extended to a maximum of once per 40 months.
3.17 -Page 2                       Amendment No. 104,4195,

TECHNICAL SPECIFICATIONS 3.0  SURVEILLANCE REQUIREMENTS 3.17 Steam Generator Tubes (Continued)
(ii)   Increased Inspection Frequencies
: 1.      If results of the in-service inspection of the steam generator tubes conducted in accordance with Table 3-13 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 a subsequent inspection meets the conditions specified in Section 3.17(3)(i)2 above, at which time the interval can be extended to a 40-month period.
(iii) Unscheduled in-service inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 3-13 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 Section 2.1.4 of the Technical Specifications,
: 2.      A seismic occurrence greater than the Operating Basis Earthquake,
: 3.      A loss-of-coolant accident requiring actuation of the engineered safeguards, or
: 4.      A main steam line or main feedwater line break.
3.17 - Page 3                      Amendment No. 104,195,

TECHNICAL SPECIFICATIONS 3.0  SURVEILLANCE REQUIREMENTS 3.17 Steam Generator Tubes (Continued)
(4)    Acceptance Criteria (i)    As used in this specification:
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.
Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.
Degraded Tube means a tube containing imperfections >20% of the nominal wall -
thickness caused by degradation. Any tube which does not permit the passage of the eddy-current inspection probe through its entire length and U-bend shall be deemed a degraded tube.
                   % Degradation means the percentage of the tube wall thickness affected or removed by degradation.
Defect means an imperfection of such severity that it exceeds the plugging limit.
Plugging Limit means the imperfection depth at or beyond which the tube shall be removed from service by plugging because it may become unserviceable prior to the next inspection. Plugging limit is equal to 40% of the nominal tube wall thickness for the original tube wall.
Unserviceable describes the condition of a tube if it leaks in excess of analyzed limits or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break.
Tube or Tubing means that portion of the tube which forms the primary system to the secondary system pressure boundary.
Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.
(ii)   The steam generator shall be determined OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 3-13.
3.17 - Page 4                       Amendment No. 104,195,

TECHNICAL SPECIFICATIONS 3.0  SURVEILLANCE REQUIREMENTS 3.17 Steam Generator Tubes (Continued)
(5)    Reporting Requirements (i)      Following each in-service inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission within 30 days.
(ii)    The complete results of the steam generator tube in-service inspection shall be reported to the Commission within 6 months following completion of the inspection.
This report shall include:
: 1.      Number and extent of tubes inspected.
: 2.      Location and percent of wall thickness penetration for each imperfection.
: 3.      Identification of tubes plugged.
(iii)   Results of steam generator tube inspections which fall into Category C-3 and require prompt notification of the Commission shall be reported prior to resumption of plant operation. The written followup of this report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
3.17 -Page 5                Amendment No. 104,195, 228,

TECHNICAL SPECIFICATIONS TABLE 3-13 STEAM GENERATOR TUBE INSPECTION 1st Sample Inspection                                  2nd Sample Inspection                3rd Sample Inspection Sample Size         Result     Action Required         Result       Action Required          Result        Action Required A minimum of           C-1              None               N/A                 N/A              N/A                  N/A 312 S.G. tubes per         C-2   Plug defective tubes and      C-1                None              N/A                   N/A Nn                 /                     /
inspect additional 624                                                                             __
tubes in this S.G.            C-2     Plug defective tubes         C-i                 None and inspect additional 1248 tubes in this S.G.      C-2      Plug defective tubes C-3     Perform action for C-3       C-3      Perform action for C-3 result of first sample                result of first sample C-3   Inspect all tubes in this The                    None              N/A                   N/A S.G., plug defective      second tubes and inspect 624     S.G. is tubes in other S.G.       C-1 Prompt notification to    The         Perform action for C-2       N/A                   N/A NRC pursuant to           second      result of second specification 5.6         S.G. is     sample C-2 The         Inspect all tubes in the     N/A                   N/A second      second S.G. and plug S.G. is     defective tubes.
C-3         Prompt notification to NRC pursuant to specification 5.6                                  46 N/   Nl applicaoie                                      3.1 _P !_b                                   Amndmn
_age    . . N.        .~lO, 19 N/A Not appilcable                                      3.17 - Page 6                                Amendment No. 46,99,104, 195

TECHNICAL SPECIFICATIONS 3.0   SURVEILLANCE REQUIREMENTS 3.17  Steam Generator Tubes (Continued)
Basis The surveillance requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be maintained. The program for in-service inspection of the steam generator tubes is based on modification of Regulatory Guide 1.83, Revision 1, dated July 1975. In-service inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or in-service conditions that lead to corrosion.
In-service 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.
Whenever the results of any steam generator tubing in-service inspection fall into Category C-3, these results will be promptly reported to the Commission prior to the 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.
3.17 - Page 7              Amendment No. 104,195,228,}}