ML20151X101

Forwards Preliminary Draft of Proposed Low Power License NPF-48,for Review & Comment.Comments Requested by 860204

ML20151X101
Person / Time
Site:	Catawba
Issue date:	02/03/1986
From:	Novak T Office of Nuclear Reactor Regulation
To:	Tucker H DUKE POWER CO.
References
NUDOCS 8602120290
Download: ML20151X101 (15)

Text

Docket No.: 50-414 Mr. H. B. Tucker, Vice President Nuclear Production Department

• D~ uke Power Company FEB 0 31986. '

42TSouth Church Street Charlotte, North Carolina 28242

Subject:

Catawba Nuclear Station, Unit 2 - Transmittal of a Preliminary Draft of the Proposed Low Power License Enclosed for your review and comment is a preliminary draft of the proposed low power license for Catawba Unit 2. A principal objective of this trans-mittal is to ensure that it accurately reflects the commitments required of Duke Power Company as described in the FSAR, SER and other documents. We expect that the_ license conditions for the low power license will be the same as those in this draft ifcense, unless a resolution is reached before issuance of the low power license.

Please provide your comments by February 4,1986. If you require any clarifi-cation of this matter, please contact the Project Manager, Kahtan Jabbour, at (301) 492-9789.

Sincerely, Original signed bgt' Thomas M. Novak Thomas M. Novak, Acting Director Division of PWR Licensino-A Office of Nuclear Reacto'r Regulation

Enclosure:

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Docket No.: 50-414 -

Mr. H. B. Tucker, Vice President Nuclear Production Department Duke Power Company 422 South Church Street Charlotte, North Carolina 28242

Subject:

Catawba Nuclear Station, Unit 2 - Transmittal of a Preliminary Draft of the Proposed Low Power License Enclosed for your review and comment is a preliminary draft of the proposed low power license for Catawba Unit 2. A principal objective of this trans-mittal is to ensure that it accurately reflects the commitments required of Duke Power Company as described in the FSAR, SER and other documents. We expect that the license conditions for the low power license will be the same as those in this draft license, unless a resolution is reached before issuance of the low power license.

Please provide your comments by February 4,1986. If you require any clarifi-cation of this matter, please contact the Project Manager, Kahtan Jabbour, at (301) 492-9789.

Sincerely, M

Thomas M. Novak, Acting C' rector Division of PWR Licensing-A Office of Nuclear Reactor Regulation

Enclosure:

As stated cc: See next page

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Mr. H. B. Tucker Duke Power Company Catawba Nuclear Station cc:

William L. Porter, Esq. North Carolina Electrifc Membership D'Re u Power Company Corp.

P 0 Box 33189 3333 North Boulevard Charlotte, North Carolina 28242 P.O. Box 27306

0. Michael McGarry, III, Esq.

Bishop, Liberman, Cook, Purcell Saluda River Electric Cooperative, and Reynolds Inc.

1200 Seventeenth Street, N.W. P.O. Box 929 Washington, D. C. 20036 Laurens, South Carolina 29360 North Carolina MPA-1 Senior Resident Inspector Suite 600 Route 2, Box 179N 3100 Smoketree Ct. York, South Carolina 29745 P.O. Box 29513 Raleigh, North Carolina 27626-0513 Regional Administrator, Region II U.S. Nuclear Regulatory Commission, Mr. C. D. Markham 101 Marietta Street, NW, Suite 2900 Power Systems Division Atlanta, Georgia 30323 Westinghouse Electric Corp.

P.O. Box 355 Pittsburgh, Pennsylvania 15230 Robert Guild, Esq.

2759 Rosewood Drive NUS Corporation Columbia, South Carolina 29205 2536 Countryside Boulevard Clearwater, Florida 33515 Palmetto Alliance 2759 Rosewood Drive Mr. Jesse L. Riley, President Columbia, South Carolina 29205 Carolina Environmental Study Group 854 Henley Place Karen E. Long Charlotte, North Carolina 28208 Assistant Attorney General N.C. Department of Justice Richard P. Wilson, Esq. P.O. Box 629

Assistant Attorney General Raleigh, North Carolina 27602 S.C. Attorney General's Office P.O. Box 11549 Spence Perry, Esquira Columbia, South Carolina 29211 Associate General Counsel Federal Emergency Management Agency Piedmont Municipal Power Agency Room 840 100 Memorial Drive 500 C Street Greer, South Carolina 29651 Washington, D. C. 20472 Mark.S. Calvert, Esq.- Mr. Michael Hirsch Bishop, Liberman, Cook, l Federal Emergency Men &oement Agenc.v Purcell & Reynolds Office of the General Zounsel 1200 17th Street, N.W. Room 840 Washington, D. C. 20036 500 C Street, S.W.

Washington, D. C. 20472 Brian P. Cassidy, Regional Counsel Federal Emergency Management Agency, l Region I J. W. McCormach POCH Boston, Massachusetts 02109 E-

[cuenq'o^ UNITED STATES 8 o NUCLEAR REGULATORY COMMISSION

• .t WASHING TON, D. C. 20555

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DUKE POWER COMPANY DRAFT NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1

-. PIEDM0NT MUNICIPAL POWER AGENCY *'

DOCKET NO. 50-414

< CATAWRA NUCLEAR STATION, UNIT 2 FACILITY OPERATING LICENSE License No. NPF-48

1. The Nuclear Regulatory Comission (the Comission or the NRC) has found that:

.e A. The application for license filed by the Duke Power Company acting for itself, North Carolina Municipal Power Agency No. I and Piedmont Municipal Power Agency (the licensees) complies with the-standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; and all required notifications to other agencies or bodies have been duly made; B. Construction of the Catawba Nuclear Station, Unit 2 (the facility) has been substantially completed in confomity with Construction Permit No.

CPPR-117 and the application, as amended, the provisions of the Act and the regulations of the Comission; C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission (except as exempted from compliance in Section 2.D. below);

D. There is reasonable assurance: (i) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be con-ducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.D.

below);

E. Duke Power Company

• is technically qualified to engage in the activities authorized by this license in accordance with the Comission's regulations set forth in 10 CFR Chapter I; F. The licensees have satisfied the applicable provisions of 10 CFR Part 140,

" Financial Protection Requirements and Irdemnity Agreements," of the Comission's regulations; , [

• Duke Power Cnmpany is authorized to act as agent for the North Carolina Municipal Power Agency No. I and Piedmont Municipal Power Agency, and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility.

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. , G. The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public; '

-- H. After weighing the environmental, economic, technical, a~nh other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of this Facility Operating ~ License No. NPF-48, subject to the conditions for protection of the environment set forth in the Environmental Protection Plan' attached as Appendix B, is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied; I. The receipt, possession, and use of source, byproduct and special nuclear 4

material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40, and 70.

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2. Based on the foregoing findings and the July 26, 1985, and the November 21, 1985, affirmations by the Atomic Safety and Licensing Appeal Board of the Partial Initial Decisions issued by the Atomic Safety and Licensing Boards dated June 22, September 18, and November 27, 1984, regarding this facility and satisfaction of conditions therein imposed, Facility Operating License No. NPF-48 is hereby issued to the Duke Power Company, the North Carolina Municipal Power Agency No. I and Piedmont Municipal Power Agency (the licensees) to read as follows:

A. This license applies to the Catawba Nuclear Station, Unit 2, a pres-surized water reactor and associated equipment (the facility) owned by the North Carolina Municipal Power Agency No. I and Piedmont Municipal

Power Agency and operated by Duke Power Company. The facility is located on the licensees' site in York County, South Carolina, on the shore of Lake Wylie approximately 6 miles north of Rock Hill, South Carolina, and is described in Duke Power Company's Final. Safety Analysis Report, as supplemented and amended, and in its Environ-mental Report, as supplemented and amended; B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:

(1) Duke Power Company, pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use, and operate the facility at the designated location in York County, South Carolina, in accordance with the procedures and limitations set forth in this license; (2) North Carolina Municipal Power Agency No. I and Piedmont Municipal Power Agency, pursuant to the Act and 10 CFR Part 70, to possess the facility at the designated location in York County, South Carolina, in accordance with the procedures and limitations set forth in this license; .

(3) Duke Power Company, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for. storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended;

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' (4) Duke Power Company, pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use at any time any byproduct,

, source and special nuclear material as sealed neutron sources for

- - reactor startup, sealed sources for reactor instru~mehtation and -

radiation monitoring equipment calibration, and as fission de-tectors in amounts as required;

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(5) Duke Power Company, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) Duke Power Company, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility authorized herein.

(7) Duke Power Company, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of McGuire Nuclear Station, Units 1 and 2, and Oconee Nuclear Station, Units 1, 2, and 3.-

C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Comission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level Duke Power Company is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thennal (100 per-cent power) in accordance with the conditions specified lerein.

The items identified in Attachment I to this license shcIl be completed as specified. Attachment 1 is hereby incorporated into this license. Pending Comission approval, this license is re-stricted to power levels not to exceed 5 percent of full power (170 megawatts thermal).

(2) Technical Specifications and Environmental Protection Plan TheTechnicalSpecificationscontainedinAppendix,A[andthe Environmental Protection Plan contained in Appendix B, both cf which are attached hereto, are hereby incorporated irito this license. Duke Power Company shall operate the facility in accord-ance with the Technical Specifications and the Fnvironmental Pro-tection Plan.

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DRAFT (3) Initial Startup Test Program (Section 14, SER, SSER ,#3)*

Any changes to the Initial Test Program described in'Section 14 of the FSAR made in accordance with the provisions of f0 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such. change.

< Antitrust Conditions (4)

Duke Power Company shall comply with the antitrust conditions delineated in Appendix C to this license. ,

(5) Inservice Inspection Program (Sections 5.2.4 and 6.6, SSER #2; Section 6.6, SSER #5)

Within six months of the date of this license. Duke Power Company shall submit the balance of the inservice inspection program as described in its letter dated January 8, 1985, for staff review and approval.

(6) Fire Protection Prooram (Section 9.5.1, SER, SSER #1, SSER #2, 55ER #3, SSER #4, 55ER #5)

(1) Duke Power Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report as amended, for the Catawba Nuclear Station and as approved in the Safety Evaluation Report (NUREG-0954) dated February 1983 and Supplement Nos. I thru 5 thereto, subject to the fol-lowing provision.

(2) Duke Power Company may not make changes to the approved fire protection program which would adversely affect the ability to achieve and maintain safe shutdown in -

the event of a fire without prior approval of the Commission.

• The parenthetical notation following'the title of many license conditions denotes the section of the Safety Evaluation Report and/or its, supplements wherein the license condition is discussed. ,

(7) Turbine Missiles (Section 3.5.1.3, SER) DRAFT Duke Power Company shall submit for NRC staff approval by December 6,1987, a turbine system maintenance program based on

_ the manufacturer's calculatinns of missile generation probabilities acceptable to the NRC staff or volumetrically inspect all low pressure turbine rotors within three years or by the second refueling

< outage, whichever is later, and thereafter every three years or every other refueling outage until a maintenance program is approved by the staff. .

(8) Detailed Control Room Design Review, I.D.1 (Section 18.1, SER, 55ER #2, SSER #5)

Duke Power Company shall correct all human engineering deficiencies according to the schedule contained in its letters dated February 20 and March 28, 1984.

(9) Emergency Response Capabilities (Generic Letter 82-33, Supplement 1 to NUREG-0737).

(a) Regulatory Guide 1.97, Revision 2, Compliance (Section 7.5.2, SSER #4, SSER #5)

Prior to startup following the first refueling outage, Duke Power Company shall provide qualified accumulator discharge instrumentation.

(b) Safety Parameter Display System (SPDS) (Section 18.2, SSER #5)

Prior to startup following the first refueling outage, Duke Power Company shall add to the existing SPDS and have oper-ational the following SPDS parameters: (a) residual heat removal flow, (b) containment isolation status, (c) stack radiation measurements, (d) primary coolant systen hot leg temperature, and (e) steam generator or stea.nline radiation.

The actual value of these and all other SPDS variables should be displayed for operator viewing in easily and rapidly accessible display formats.

(10) Anticipatory Reactor Trip, II.K.3.10 (Section 5.2.2, SER)

Prior to exceeding 70% power, Duke Power Company shall complete the described turbine trip tests to verify that PORVs will not be challenged when the anticipatory trip bypass is in effect.

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1 (11) Steam Generator Tube Ruoture (Section 15.4.4, SER, SSER #2)

Prior to startup following the first refueling outage of Catawba

- . Unit 2, Duke Power Company shall submit for NRC stliff review and '

- approval an analysis which demonstrates that the steam generator ,

single-tube rupture analysis presented in the FSAR is' the most severe case with respect to the release of fission products anB~

< calculated doses. Consistent with the analytical assumptions, Duke Power Company shall propose any necessary changes to Appendix A to this license.

(12) Transamerica Delaval, Inc. (TDI) Diesel Generators (Section 8.3.1, 55ER #4, 55ER #5) i Duke Power Company shall implement the TDI diesel requirements as F specified in Attachment 2. Attachment 2 is hereby incorporatet 1

into this license.

(13) Generic Letter 83-28 (Section 15.6, SSER #4, SSER #5) 1 Duke Power Company shall submit responses to and implement the guidance of Generic Letter 83-28 on a schedule which is con-sistent with that given in its November 2 and December 31, 1984, letters.

D. The facility requires exemptions from certain requirements of Appendices A, E, and J to 10 CFR Part 50, as delineated below, and pursuant to evaluations contained in the referenced SER and SSERs. These include (a) partial exemption from General Design Criteria 16, 38, and 50 of Appendix A, with respect to the completion and testing of the ice condenser prior to the reactor coolant system temperatures exceeding 200'F (mode 4), as required by Technical Specifications (Section 6.2.1 of SSER 5), (b) exemption from the requirements of Appendix E, IV.F. insofar as they may require the active participatton of all Crisis Management Center personnel for the Catawba Station emergency-preparedness exercises (Section 13.3 of SSERs 4 and 5), (c) partial exemption from the requirement of paragraph III.D.2(b)(ii) of Appendix

J, the testing of containment airlocks at times when the containment i integrity is not required (Section 6.2.6 of SSER 5), (d) exemption from the requirement of paragraph III. A.(d) of Appendix J, insofar as it requires the venting and draining of lines for type A tests (Section.

6.2.6 of SSER 5), and (e) partial exemption from the requirements of 4 paragraph III.B of Appendix J, as it relates to bellows testing (Sec-tion 6.2.6 of the SER, and Section 6.2.6 of SSER 5). These exemptions are authorized by law, will not present an undue risk to the public

healthandsafety,andareconsistentwiththecommonde,fegseand 4

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. l security; and certain special circumstances are present. These exemptions are, therefore, hereby granted pursuant to 10 CFR 50.12.

With the granting of these exemptions, the facility will* dperate, to the extent authorized herein,-in conformity with the application, as amended, the provisions of theJAct, and the rules and' regulations of the Comission. In addition a partia) exemption from those portions e of General Design Criterion 4 of Appendix A to 10 CFR 50 which re-quire protection of structures, systems and components against dynamic effects associated with postulated reactor coolant system pipe breaks.

This exemption was granted on April 23, 1985, pursuant to 10 CFR 50.12 for a period ending with the completion of the second refueling outage for Catawba Unit 2 or the adoption of the proposed rulemaking for

, modification of GDC-4 whichever occurs first.

E. Duke Power Company shall fully implement and maintain in effect all provisions of the Commission approved physical security, guard train-ing and qualification, and safeguards contingency plans including amendments made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: " Catawba Nuclear Station Security Plan," with revisions submitted through November 11, 1985; " Catawba Nuclear Station Guard Training and Qualification Plan," with revisions submitted through September 30, 1985; and " Catawba Nuclear Station Safeguards Contingency Plan," with revisions submitted through October 23, 1985.

F. Reporting to the Commission Duke Power Company shall report any violations of the requirements contained in Section 2. Items C.(1), C.(3) through C.(15) of this license. Initial notification shall be made within twenty-four (24) hours in accordance with the provisions of 10 CFR 50.72 with written follow-up within 30 days in accordance with the procedures described in 10 CFR 50.73 (b), (c), and (e).

G. The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

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8-H. This license is effective as of the date of issuance and shall expire at midnight on '

FOR THE NUCLEAR REGULATORY ' COMMISSION .

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Harold R. Denton, Director Office of Nuclear Reactor Regulation

Enclosures:

1. Attachment 1

2. Attachment 2

3. Appendix A - Technical Specifications

4. Appendix 8 - Environmental Protection Plan

5. -Appendix C - Antitrust Conditions Date of Issuance:

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ATTACHMENT'1 TO LICENSE NPF-48 DETAILS TO BE PROVIDED AS APPROPRIATE - I BY REGION II D' k l -

ATTACHMENT 2 TO LICENSE NPF-48 g!Q nJ1l E TDI DIESEL ENGINES REQUIREMENTS Duke Power Company shall comply with the following requirements'rdlated to the" TDI diesel engines for Catawba Unit 2.

1. . Changes to the maintenance and surveillance program for* the TDI diesel

< engines, as identified and approved by the NRC staff in Supplement 5 to the SER, shall be subject to the provisions of 10 CFR 50.59.

2. Connecting rod assembifes shall be subjected to the following inspec-tions at each major engine disassembly (approximately every 5 years):

The clearance between the link pin and the Ifnk rod should be examin0d. This dimension must be zero when the specified bolt torque is applied.

The surfaces of the rack teeth should be inspected for signs of fretting. If fretting has occurred, it should be subject to an engineering evaluation for appropriate corrective action. The mating surfaces should also be examined to ensure that the percentage of contact meets manufacturer's recommendations.

All connecting-rod bolts should be lubricated in accordance with the engine manufacturer's instructions and torqued to the speci-fications of the manufacturer (e.g.,1700 ft - lb). The lengths of the two pairs of bolts above the crankpin should be measured ultrasonically pre- and post-tensioning.

If connecting-rod bolt stretch was measured ultrasonically during reassembly following the preservice inspection, the lengths of the two pairs of bolts above the connecting rod should be remeasured ultrasonically before the link rod box is disassembled. Alternatively, the breakway torque should be -

! measured. If bolt tension detemined by either method is less than 93% of the value at installation, the cause should be detemined, appropriate corrective action should be taken, and the interval between checks of bolt torque should be reevaluated.

All connecting rod bolts should be visually inspected for thread l damage (e.g., galling), and the two pairs of connecting rod bolts above the crankpin should be MT inspected to verify the continued absence of cracking. All washers used with the bolts should be examined visually for signs of galling or cracking, and replaced

, if damaged.

A visual inspection should be performed of all extern'al surfaces of the link rod box to verify the absence of any signs 6f service induced distress.

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. DRAFT All of the bolt holes in the link rod box should be inspected for thread damage (e.g., galling) or other signs of abnomalities. In addition, the bolt holes subject to the highest stresses (i.e., the

2- ' pair imediately above the crankpin) should be examin~ed with an appropriate nondestructive method to verify the continued absence of cracking. Any indications should be recorded for engineering-Evaluation and appropriate corrective action.

3. Cylinder blocks shall be inspected at intervals calculated using the cuculative damage index (CDI) model and using inspection methodologies described by Failure Analysis Associates, Inc., (FaAA) in report entitled " Design Review of TDI R-4 Series Emergency Diesel Generator Cylinder Blocks" (FaAA-84-9-11) dated December, 1984. Liquid penetrant inspection of.the cylinder liner landing area should be perfomed anytime liners are removed. If inspection reveals cracks in the cylinder block between stud holes of ad.iacent cylinders, this 4

condition shall be reported promptly to the NRC staff and the affected engine shall be considered inoperable. The engine shall not be restored to " operable" status until the proposed disposition and/or corrective actions have been approved by the NRC staff.

4. The engines shall be rolled over with the airstart system and the cylinder stopcocks open prior to any planned starts, unless that start occurs within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of a shutdown. The engines shall also be rolled over with the airstart system and the cylinder stopcocks open after 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, but no more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after engine shutdown and then rolled over once again approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after each shutdown. In the event an engine is removed from service for any reason other than the rolling over procedure prior to expiration of the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> periods noted above, that engine need not be rolled over while it is out of service. The licensee shall air roll the engine over with the stopcocks open at the time it is returned to service. The origin of any water detected in the cylinders must be detemined and any cylinder head which leaks due to a ~ crack shall be replaced. No cylinder heads that contain a through-wall weld repair where the repair was perfomed from one side only shall be used on the engines.

5. Periodic inspections of the turbochargers shall include the followirg:

4 The turbocharger thrust bearings should be visually inspected for excessive wear after experience 40 non-prelubed starts since the previous visual inspection.

Turbocharger rotor axial clearance should be measured at each refueling outage specifications. to verify compliance with TDI/Elliot,In addition, thrust bear be compared with measurements taken previously to deterr6fne whether trend exists. Any such trends shall be evaluated by the licensee to determine need for further inspection at corrective action.

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- r-DRAFT Spectrographic and ferrographic engine oil analysis shall be performed quarterly to provide early evidence of thrust bearing degradation. Particular attention should be paid to copper level and particulate size which could signify thrust bearing

. degradation.

The nozzle ring components and inlet guide vanes should be

,- visually inspected at each refueling outage for missing parts or parts showing distress. If such are noted, the entire ring assembly should be replaced.

Pre-turbine exhaust temperature shall be monitored during engine operation to ensure that the manufacturers temperature limit is not exceeded.

6. Main bearing No. 7 of emergency diesel generator 28 shall be dis-assembled and inspected at each refueling outage, both visually and with liquid penetrant. Subsequent to reassembly and run-in testing in accordance with manufacturers recomendations, but prior to considering the engine to be operable, the No. 7 bearing cap and upper bearing shell shall be removed. Visible edges of the lower shell and the upper shell shall be visually inspected to ve_rify that the bearings are free of distress. Operation beyond the first refueling outage shall reouire staff approval based on the staff's final review of the Owners Group generic findings and of the overall implementation status of Owners Gr6up recommendations at Catawba 2.

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