ML20151U501

Special Rept 88-09:during Dec 1987 & Jan 1988,annual Surveillance of Reactor Bldg Surfaces Made

ML20151U501
Person / Time
Site:	Rancho Seco
Issue date:	04/18/1988
From:	Firlit J SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
88-09, 88-9, AGM-NPP-88-280, NUDOCS 8805020078
Download: ML20151U501 (5)

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SACRAMENTO MUNICIPAL UTILITY DibTRiCT C P. O. Box 15830, Sacramento CA 95852 1836, 16) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CAllFORNIA i ,.

AGM/NPP 88-280 E' N APR 181358 U. S. Nuclear Regulatory Commission Attn: J. B. Hartin, Regional Administrator Region V

. 1450 Maria Lane, Suite 210 Halnut Creek, CA 94596 SPECIAL REPORT NUMBER 88-09: ANNUAL SURVEILLANCE OF REACTOR BUILDING SURFACES

Dear Sirs:

The Sacramento Hunicipal Utility District hereby submits Special Report Number 88-09 in accordance with Rancho Seco Nuclear Generating Station Technical Specification 6.9.5 B.l. 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.

Please contact me if you have any questions. Members of your staff with questians requiring additional information or clarification may contact Mr. Gary Aron at (916) 452-2211, extension 4759.

Sincerely, w

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Joseph F. Firlit Assistant General Manager, Nuclear Power Production Attachment cc: G. Kalman, NRC, Rockville (w/atch)

A. D'Angelo, NRC, Rancho Seco ( )

F. J. Hiraglia, NRC, Rockville ( "

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ADCtCK 05000312 DCD RANCHO SECO NUCLEAR GENERATING STATION O 1444o Twin Cities Road, Herald, CA 95G38 9799; (209) 333 2935

l l . , i, e SPECIAL REPORT 88-09 Annual Surveillance of Reactor Building Surfaces Surveillance Procedure SP.1010 "Annual Surveillance of Reactor Building (RB) Interior and Exterior  ;

Sntfaces."

Surveillance Dates December 1987 and January 1988 Qescriotion of Surveillance All levels of the Reactor Building exterior were visually examined for ,

evidence of excessive concrete cracking, corrosion, or any other development which mi';ht affect the structural integrity of the building, with special .

attentia.1 given to the tendon anchorage areas in and around buttresses and the  !

l ring girder. Also examined were the Reactor Building dome and the tendon i

access gallery.

Specific areas of the exterior of the Reactor Building where discontinuities occur (penetration areas, equipment hatch, personnel hatch, etc.) were i visually examined. The inspection was performed to determine if there is any  ;

evidence of strain concentration or excessive cracking. This included j 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, t 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.

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

S.urveillance Results ,

i General Visual Inspection of Exterior Surfaces Walk Around Inspection: Exterior of reactor surfaces appears to be in good shape. No major cracks observed. A few hairline cracks around tendon trumpets and numerous grease leaks from under tendon anchor plates.

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i Reactor Building Dome Inspection: The coating around 59 tendon caps has cracked and is in need of repair. Two hairline cracks run around the dome about 5 to 6 ft. apart. Numerous scuffs and cracks around dome coating. Horizontal hairline crack runs across buttress #3 at 125 ft.

elevation.

Tendon Access Gallery Inspection: There are many hairline cracks throughout the gallery. There is no appearance of any new cracks or  ;

expansion of old ones. There is a small amount of debris in all (3) .

shafts and gallery.

j Specific Area Inspection of Exterior Surfaces Area 1, Grade Level - area surrounding _the equipment hatch: No change from last year. Grease leak north of equipment hatch has been patched.

Seems to be stabilized.

Area 2, Grade Level - area surrounding the emergency hatch: No cracks or [

i grease leaks observed.

Area 3, Grade Level - area in the vicinity of the A Main Steam Line: No l cracks around (A) Hain Steam Line. A few tendon vents leaking grease.

Not considered significant.

I Area 4, Grade Level - area in the vicinity of B Hain Steam Line: No cracks around (B) Main Steam Line.

) Area 5, Grade Level - area in the vicinity of the electrical penetrations: This area in good condition. No cracks noted.  !

Area 6, +20 ft. Level - area in the vicinity of purge inlet and outlet [

and electrical penetrations: This vicinity in very good condition. No cracks.

Area 7, +20 ft. Level - area in the vicinity of electrical penetrations:

No cracks observed in this area.

) Area 8, +40 ft. Level - area in the vicinity of the personnel hatch:  !

Expansion material damaged in a few places. Should be replaced.  ;

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I Area 9, +40 ft. Level - area in the vicinity of the plant exhaust: No  !

cracks in this area.

, Area 10. -20 ft. Level - area in the West Decay Heat Cooler Room:

Numerous hairline cracks run from penetration to penetration.

Area 11, -20 ft. Level - area in the East Decay Heat Cooler Room: A

vertical crack from two unnumbered penetrations located atout 2 f t, east

] of penetrations #56 and #3. These tracks were present last year and haven't expanded, t

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Area 12. -37 ft. Level - Area in the vicinity of the Reactor Building

. Emergency Sump Line to B Decay Heat Pump suction: Same crack as last year. No' expansion, i

Area 13. -37 ft. Level - area in the vicinity of the Reactor Building Emergency Sump Line to A Decay Heat Pump suction: Same cracks as last year. No expansion.

General Visual Inspection of Interior Surfaces

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Halk Around Inspection:

-24 ft. to Grade '

Several penetrations at this elevation are showing rust. Several coolant pipes at this elevation are losing their protective coating strips and .

large flakes of coating are barely adhering to the pipes. The emergency sump is partially filled with water. The trench at -23 ft. is partially filled with debris. Liner plate is nicked and chipped all the way around from elevation -24 ft. to -26 ft. Angle iron supporting grating is rusting at elevation -12 ft.

Grade to +20 ft.

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{ Equipment hatch welds to liner plate are rusting through coating in a few l locations. There are several nicks in coating immediately north of i equipment hatch where scaffolding is being stored. Nicks are exposing liner plate.

) +20 ft. to +40 ft.

The ledger angle supporting grating is rusting in several locations. The J liner plate between 225 degrees to 250 degrees elevation +37 ft to +40 ft. is rusted. This area is inaccessible due to concrete slab.

+40 ft. to +60 ft.

! Working platform over the pool has debris in catch-all corners.

! i l +60 ft. to Center of Dome 1

! l Discoloration of liner plate is present throughout the entire surface and I

is rusty in color.

f j Summary ,

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i At all elevations where concrete has been placed adjacent to liner plate,

) the liner plate is rusted. It appears the liner plate was never coated t

in these areas. All elevations where concrete floors are adjacent to liner plate contain a small amount of debris. Ttie ledger angles at all ,

1 elevations are rusting in sev eal locations. The component coolant i

< piping is losing its protective coating at all elevations.

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The air handling units at o20 ft. elevation have debris lying on top of them. The horizontal cable trays have accumulated a significant amount of dust. The coating on the liner plate appears to be sound. There does not appear to be any cracking or splitting of the coating. The only exception is the rusted areas and areas where the coating has been damaged, leaving nicks and scratches. This occurs in numerous places throughout the building. The deformation or bulges of the liner plate are numerous. They run both horizontally and vertically, but appear to be from the original construction. The coating on concrete floors at all elevations except +20 ft, where grating is installed is worn through, exposing concrete in several locations.

Penetration Area Inspection: All penetrations are in good shape. A few hairline cracks, but no structural damage.

Reactor Building Dome Inspection: No structural damage. Tie back eye hook for jib crane is badly bent. Damage to liner plate indeterminate due to inaccessibility.

Specific Area Inspection of Interior Surfaces Three feet above and below the horizontal center line extending 10 ft.

east of the east edge of the personnel lock: Old liner plate bulge 6 ft.

east of east edge running vertically 40 ft. to 60 ft. No apparent deformations or paint cracking.

Two foot radius around electrical penetration No. 7: No abnormal conditions in this area.

Upper half of mechanical penetration No. 40 (main steam) extending from edge of penetration to 6 ft. out from edge: No cracks in welds of this penetration. Area in very good condition.

Two foot radius around mechanical penetration No. 20 (HP Injection): No abnormal conditions in this area.

Sumuy SP.1010 was conducted during December 1987 and January 1988. A general visual )

inspection and specific area inspection were performed for both the exterior I and interior Reactor Building surfaces for cracks, corrosion, and general deterioration.

One NCR and two work requests were written as a result of this surveillance. I NCR S-7604 was written against the badly bent jib crane tie back eye hook. It has been dotermined that the jib crane tie back eye hook is acceptable as is.

The work requests were for repairs unrelated to the integrity of the Reactor Building.

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 SP.1010.