ML20247E560

Submits Special Rept 89-09 Reporting Results of Jan & Feb 1989 Surveillance of Reactor Bldg Interior & Exterior Surfaces.Coolant Pipes Losing Protective Coatings on Interior Surfaces & Concrete Adjacent to Liner Plate Rusted

ML20247E560
Person / Time
Site:	Rancho Seco
Issue date:	05/05/1989
From:	Keuter D SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
AGM-NPP-89-165, NUDOCS 8905260293
Download: ML20247E560 (4)

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SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street, P.o' Box 15830, Sacramento'CA 8 1830,(916) 452-3211 AN ELECTRIC SYSTEM SERVING 7ftE,HgART OF CALIFORNIA 8S P.Y 9 AS: qj AGM/NPP 89-165 May 5, 1989 U. S. Nuclear Regulatory Commission Attn: J. B. Martin, Regional Administrator Region V.

1450 Maria Lane, Suite 210 Walnut Creek, CA 94596 Docket No. 50-312 Rancho Seco Nuclear Generating Station License No. DPR-54 SPECIAL REPORT NUMBER 89-09: ANNUAL SURVEILLANCE OF REACTOR BUILDING SURFACES

Dear Mr. Martin:

The Sacramento Municipal Utility District hereby submits Special Report Number 89-09 in accordance with Rancho Seco Nuclear Generating Station Technical Specification 6.9.5.B.1 on the annual surveillance of Reactor Building surfaces. The surveillance met the acceptance criteria of Surveillance Procedure SP.1010 " Annual Surveillance of Reactor Building (RB) Interior and Exterior Surfaces" and the requirements of Rancho Seco Technical Specifications.

Members of your staff with questions requiring additional information or clarification may contact Ms. Marla Mueller at (209) 333-2935, extension 4681.

Sincerely, l.

i Dan.R. Keuter i I

Assistant General Manager i Nuclear Plant Manager Attachment cc w/atch: A. D' Angelo, NRC, Rancho Seco Document Control Desk, Washington DC 0905260293 890505 D PDR ADOCK 05000312 ft S PNU ;L g

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RANCHO SECO NUCLEAR GENERATING STATION O 14440 Twin Cities Road, Herald, CA 95638-9799;(209) 333-2935

.. t SPECIAL REPORT NUMBER 89-09 Annual Surveillance of Reactor Building Surfaces Surveillance Procedure SP.1010 " Annual Surveillance of Reactor Building (RB) Interior and Exterior Surfaces."

Surveillance.Datei January and February 1989 Description of Surveillance All. levels of the Reactor Building exterior were visually examined for evidence of excessive concrete cracking, corrosion, or any other development which might affect the structural integrity of the building, with special attention given to the tendon anchorage areas in and around buttresses and the ring girder. Also examined were the Reactor Building dome and the tendon access gallery.

Specific areas of the exterior of the Reactor Building where discontinuities occur (penetration areas, equipment hatch, personnel hatch, etc.) were visually examined. The inspection was performed to determine if there is any evidence of strain concentration or excessive cracking. This included examinations at grade, +20 f t., +40 f t. , -20 f t. and -37 f t. levels.

The interior surfaces of the containment structure were visually examined for any evidence of liner plate deformation, corrosion, or any other development which might affect the structural integrity of the Reactor Building. All accessible levels of the interior of the Reactor Building were examined, including the liner plate areas of the 36 polar crane supports, all penetrations and areas where the spray header and upper dome circulators are fastened.

A visual examination was also made of the interior of the Reactor Building at areas where discontinuities occur for indication of strain concentration.

Specific attention was paid to any large deformation, liner cracking, and cracking paint.

Surveillance Results General Visual Inspection of Exterior Surfaces Walk Around Inspection: Exterior concrete surfaces appear to be in good condition. No signs of large cracks or deterioration. The following observations were made:

1. Working counterclockwise from the center of buttress No. 1, bottom group of dome tendons, 5th and 6th dome tendons have old grease leaks.

2. Small old grease leak midway between buttresses 1 and 3 and above ring girder.

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. SPECIAL REPORT NUMBER 89-09 l Annual Surveillance of Reactor Building Surfaces

3. Working clockwise from the center of buttress No. 3, bottom group, 7th dome tendon has old grease leak.

4. Working clockwise from the access ladder to the top of the Reactor Building, 1st dome tendon has a grease leak. This may be a new leak. )

Summary: Exterior concrete surfaces appear to be in good condition. No signs of large cracks or deterioration.

Reactor Building Dome Inspection: Coating needs to be repaired in several locations. Lighting arrester needs to be reinstalled.

Tendon Access Gallery Inspection: Hinor grease leaks were observed in two tendon covers in lower gallery. New grease leaks were observed in 3A and 2A access shafts.

Specific Area Inspection of Exterior Surfaces Area 1, Grade Level - area surrounding the equipment hatch: Old grease leak observed.

Area 10, -20 ft. Level - area in the West Decay Heat Cooler Room: Several hairline cracks were observed between penetrations in this area. Nothing of a serious nature (old cracks).

Area 11, -20 ft. Level - area in the East Decay Heat Cooler Room: Hairline cracks were observed between penetrations. Nothing of a serious nature; these '

are old noted cracks.

Area 12. -37 ft. Level - area in the vicinity of the Reactor Building Emergency Sump Line to B Decay Heat Pump suction: There is an old crack that has been previously documented in other surveillance reports. The crack does not appear to have grown since the last surveillance.

Area 13, -37 ft. Level - area in the vicinity of the Reactor Building Emergency Sump Line to A Decay Heat Pump suction: There are two old cracks that have been previously documented in other surveillance reports. The cracks do not appear to have grown since the last surveillance.

General Visual Inspection of Interior Surfaces Walk Around Inspection:

-27 ft.: Several penetrations are showing signs of rusting. Several coolant pipes are losing their protective coatings. Liner plate if nicked and chipped all the way around elevation -24 ft. .

At elevation -10 ft., 10 ft west of elevator shaft, coating is failing in an area of approximately 20 square ft.

(note this is a new finding).

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,. , SPECIAL REPORT NUMBER 89-09 Annual Surveillance of Reactor Building Surfaces

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1 Grade to +20 ft.: Equipment hatch welds are rusting through liner plate coatings. Several nicks around hatch due to th-down bolts being thrown against liner plate.

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+40 ft. to +60 ft.: Nicks and scratches on-liner plate.

+60 ft to Center of Dome: The usual nicks and scratches on liner plate are present. The coating of liner plate is discolored throughout the entire surface (rusty in color).  ;

Summary: All elevations where concrete has been placed adjacent to liner plate is rusted. The ledger angles supporting gratings at all elevations are rusting. The component coolant piping at all elevations is losing its protective coating. Bolting for the piping (Dresser couplings) is badly rusted at all elevations. Initial coating of liner plate appears to be sound, although it is discolored. Where coating has been applied over initial coatings, escape lock and elevation -10 ft., 10 ft. west of elevator shaft, the coating seems to be failing, exposing the initial coatings.

Penetration Area Inspection: Penetrations look good except for Component Cooling Hater lines heavily rusted.

Specific Area Inspection of Interior Surfaces I Three feet above and below the horizontal centerline extending 10 ft. east of the east edge of the personnel lock: Old liner plate bulge still present at this location. No apparent change.

Summary SP.1010 was conducted during January and February 1989. A general visual inspection and specific area inspection were performed for both the exterior and interior Reactor Building surfaces for cracks, corrosion, and general deterioration.

Two work requests were written as a result of this surveillance. The work requests are to repair the lighting arrester on the dome and to repair coatings on the dome. A program to repair the damaged coating on the interior surfaces of the Reactor Building and a schedule is being developed.

No abnormal conditions were found that would affect the Reactor Building's structural integrity or leak tightness. No significant deterioration was found. The Reactor Building was found to meet the acceptance criteria for 4 SP.1010. ]

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