ML15261A184

Informs That Staff Scheduled to Visit Plant Site on 970427-30 to Support NRC Review of Plant,Units 1,2 & 3 Reactor Bldg License Renewal Evaluation

ML15261A184
Person / Time
Site:	Oconee
Issue date:	04/15/1998
From:	Charemagne Grimes NRC (Affiliation Not Assigned)
To:	Mccollum W DUKE POWER CO.
Shared Package
ML15261A183	List: ML15261A182 ML15261A184
References
TAC-M99121, TAC-M99122, TAC-M99123, TAC-M99141, NUDOCS 9806100183
Download: ML15261A184 (5)

Text

e P.UNITED STATES T

0NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 44 April 15, 1998 Mr. William R. McCollum, Jr.

Vice President, Oconee Site Duke Power Company P.O. Box 1439 Seneca, South Carolina 27679

SUBJECT:

SITE VISIT TO SUPPORT THE NRC'S REVIEW OF THE OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3, REACTOR BUILDING LICENSE RENEWAL EVALUATION (TAC NOS. M99121, M99122, M99123, AND M99141)

Dear Mr. McCollum:

The Nuclear Regulatory Commission (NRC) staff is scheduled to visit the Oconee site April 27-30, 1998, to support its review of Duke Energy Corporation's (Duke's) reactor building evaluation contained in OLRP-1001, "License Renewal Technical Information Topical Report,"

Revision 1. The intent of the visit is to review documentation supporting the submittal, talk with knowledgeable Duke personnel, tour the reactor building to the extent possible, and discuss Duke's January 14, 1998, response to the staff's request for additional information. Topics of interest to the staff are identified in the attachment. This visit and the attachment were coordinated with Mr. Robert Gill of your staff.

The staff is aware that Oconee Unit 2 is currently in a refueling outage. The staffs intent is not to adversely impact outage activities but to complete as many of the activities identified in the attachment as Duke can support. No special provisions such as erection of scaffolding or opening of equipment is expected.

We appreciate Duke's support of this site visit. The information gained will help the staff prepare the safety evaluation for the reactor building and develop the processes and inspection programs needed to complete the staffs review of an Oconee license renewal application.

Sincerely, Christopher I. Grimes, Director License Renewal Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270 and 50-287

Enclosure:

As stated cc: See next page 9906100183 980605 PDR ADOCK 05000269 P

PDR

Oconee Nuclear Station Units 1, 2, and 3 cc:

Mr. Paul R. Newton Mr. Ed Burchfield Duke Power Company, PB05E Compliance 422 South Church Street Duke Power Company Charlotte, North Carolina 28242-0001 Oconee Nuclear Site P.O. Box 1439 J. Michael McGarry, Ill, Esquire Seneca, South Carolina 29679 Winston and Strawn 1400 L Street, N.W.

Ms. Karen E. Long Washington, DC 20005 Assistant Attorney General North Carolina Department of Mr. Robert B. Borsum Justice Framatome Technologies P.O; Box 629 Suite 525 Raleigh, North Carolina 27602 1700 Rockville Pike Rockville, Maryland 20852 Mr. L.A. Keller Manager, LIS-EC50

Manage, LISDuke Power Company NUS Corporation 526 South Church Street 2650 McCormick Drive, 3rd Floor Charlotte, North Carolina 28242-0001 Clearwater, Florida 34619-1035 Richard Fry, Director Regional Administrator, Region II Division of Radiation Protection U.S. Nuclear Regulatory Commission North Carolina Department of Environment, Atlanta Federal Center Health, and Natural Resources 61 Forsyth Street, S.W., Suite 23T85 P.O. Box 27687 Atlanta, Georgia 30303 Raleigh, North Carolina 27611-7687 Senior Resident Inspector Mr. Douglas J. Walters U.S. Nuclear Regulatory Commission Nuclear Energy Institute Route 2, Box 610 17761 Street NW.

Seneca, South Carolina 29678 Suite 300 Washington, D.C. 20006 Max Batavia, Chief Bureau of Radiological Health South Carolina Department of Health

. and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 County Supervisor of Oconee County WaShalla, South Carolina 29621

Oconee Site Visit A.

Inside Containment -

Unit 2

1.

Basemat - general surface condition and perimeter of intersection with liner plate, including joint sealant at location(s) where degradation was discovered in Units 1 and 3. (Purpose: Verify stated condition of basemat and joint sealant and gain understanding of sealant degradation.)

2.

Liner plate - overall and at the following specific locations: at crane elevation; at operating floor; at penetrations for hatches, piping and electrical; at junctures with platforms/concrete floors.

(Purpose: Verify condition and completeness of coatings and lack of corrosion.)

3.

Structural attachments to liner plate - sample of piping, electrical, cable tray/conduit, HVAC duct, instrumentation, and any other significant structural attachments, including some areas of the liner plate behind attachments that is not coated.

(Purpose: Verify condition at structural attachments.)

4.

Equipment hatch and personnel airlock - hinges, locking mechanisms, eye bolt closures.

(Purpose: Verify condition of hinges, locks, eyebolt closures, etc. which are potentially subject to mechanical wear:)

5.

Specific locations in Unit 2 which correspond to documented occurrences of degradation in C.2 and C.3 below.

(Purpose: Verify evaluation and corrective actions.)

B.

Containment Exterior -

Units 1, 2 and 3

1.

Tendon anchors in tendon gallery and on the dome (Purpose: Verify conditions of tendon anchor components.)

2.

Locations of known grease leakage through exterior of walls (Purpose: Observation of existing condition from ground level for location and extent of grease leakage.)

3.

Exterior perimeter of containment at ground level (Purpose: Verify condition of containment concrete components.)

4.

Exterior perimeter of containment at intersection with basemat, where accessible through attached buildings (Purpose: Verify condition of containment concrete components.)

Enclosure

5.

Buttresses for hoop tendons (Purpose: Verify condition based on observation from ground level.)

6.

Penetrations for hatches, piping, electrical, etc., outside of containment (Purpose: Verify condition of containment penetrations.)

7.

Upper elevations/ring girder/dome (Purpose: Verify condition of containment concrete components, including evidence of potential radial shear of center of dome.)

C.

Documentation

1.

Results of the latest Appendix J integrated leak rate test and tendon surveillance test.

2.

LERs related to containment degradation.

3.

Maintenance and inspection records and site issues reports for the containments related to aging degradation for the last 5 years.

4.

Site procedures, including coating monitoring and joint sealant maintenance programs, for inspecting containment, including inaccessible areas, and determining appropriate corrective actions.

5.

Groundwater sampling test results.

D.

Discussion with plant personnel

1.

Operating experience with containment degradation.

2.

Evaluation methodology for structural integrity, including loss of structural stiffness and strength, due to potential aging degradation.

3.

Discussion about selection of random tendons to pursue the trend analysis for the 60 year renewal period, frequency of readings, etc.

,4. Plans for the first inservice inspection under IWE and IWL as a part of 50.55a rule.

5.

Interpretation of ASME Section XI containment evaluation boundary for attachment details.

6.

Tendon grease leakage: method of monitoring, evaluation of source and leak rate, grease formulation, results of any tests/evaluation performed.

7.

Corrosion allowance of liner plate: corrosion allowance in design, nominal plate thickness, and evaluation of corrosion in Units 1 and 3 (A.1 above) and basis for acceptance criteria.

8.

Operating experience of dome drainage system: occurrences of blockage, cause, assessment of effects, corrective actions to preclude recurrences.

9.

Prior assessment of potential for radial shear failure of center of dome.

10.

Implementation of maintenance.rule (50.56) regarding the containment structure.