Text

Forwards Trip Rept Re NRC Audit of Plant During Wk of 920615
	ML20114D455
Person / Time
Site:	Beaver Valley
Issue date:	07/24/1992
From:	Braverman J; BROOKHAVEN NATIONAL LABORATORY
To:	Polk H; NRC
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ML20105C655	List: ML20114D455;
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	CON-FIN-L-1521 NUDOCS 9209080211
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BROOKHAVEN NATIONAL LABORATORY, _

] {7 } ASSOCIATED UNIVERSITIES, INC.

Upton. Long Island, New York 11973 (516)282s Department of Nuclear Energy FTS 666' 2186 FAX (516)282-4255 4

July 24, 1992 4

, l Mr. Harold Polk U.S. Nuclear Regulatory Commission Mail Stop 12-H26 Washington, DC 20555 '

Dear Mr. Polk:

Subject:

Beaver Valley Power Station _ Trip _ Report; Assessment ofJ Structures and Civil' Engineering-Features a 't-_ Operating Plants; FIN L-1521, Task Assignment No._6 Enclosed please find a copy of the trip report for the NRC.

audit of Beaver Valley. Power Station, Unit 1,-which-was conducted during the week of June 15, 1992.

If you have any questions or comments'on this-report, please feel free.to call me.

Sincerely- -yours , .

4 stew Joseph Braverman Engineering Research-and Applications: Division

\kb Enc.

cc:' G. Bagchi (NRC)

R. Rothman-(NRC)_

J. Ma-:(NRC)

M. Reich _(BNL)

C. Hofmayer- (BNL)

P. - Bezler-. (BNL)'

R. Morante -(BNL)

4 8 ENCLOSURE BEAVER VALLEY POWER STATION UNIT 1 TRIP REPORT

Purpose:

Audit of Structures and Civil Engineering Features Location: Beaver Valley Power Station Unit 1 Shippingport, Pennsylvania Date: June 15-19. 1992 '

Personnel: R. Rothman (NRC), J. Ma (NRC), J. Carrasco (NRC),

R. Morante (BNL) , J. Braverman (BNL)

Backarounct The objective of the plant visit was to obtain information about the performance-of structures at operating plants and to draw some generic conclusions based on the information obtaine.d from this and other plant visits. _ To achieve this objective, an assessment of the existing condition and past performance of structures and civil engineering features at Daaver Valley Power Station was performed. Any failures, degradations, maintenance, surveillance, modifications / repairs of safety related-structures were of interest. Structures reviewed include buildings, tanks, cable tray and conduit supports, anchorages, underground structures, and the water intake structure.

Inspection Summary This section of the trip report describes the-various audit activities and the structures that were examined during the walkdown. The section following this inspection summary presents the results and major observations noted during the audit. A more complete list and detailed description ' of the observations are '

contained in Attachment 1.

June 15. 1992: '

At 2:00 p.m. , the audit team met with Al DeAgazio, NRC Project Manager, at the plant site. The BNL members of the team were given site-specific safety training, which is required. for escorted visitors.

The NRC members of thc team completed necessary paperwork for unescorted access to the plant. Badging and dosimetry procedures 1

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J were reviewed with the audit team and camera passes were requested for the walkdown.

lyne 16. 1992:

At 8:00 a.m., there was a brief entrance meeting. This was followed by a formal presentation by Duquesne Light Company _-(DLCo) personnel. The attendee list is contained in Attachment 2. A copy

of the agenda and viewgraphs used in the presentation is included l in Attachment 3. The major topics covered include design criteria, 4 containment structure, support anchorages, spent fuel pool / racks, intake structure, masonry walls, ground water issues, buried

piping, storage tanks, civil / structural LERs and 10 CFR 50.59 evaluations, and plant safety procedures for natural phenomena.

June 17 1992:

The walkdown was initiated at 8:00 a.m. The audit team remained together throughout the plant walkdown activities. BNL l personnel were escorted by R. Rothman, NRC. DLCo engineering-and maintenance personnel were assigned to guide us through the plant and to answers questions as they came up. If questions could not be irmediately answered, they were recorded for followup by the plant staif.

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The first area visited was the Irtake Structure, which is enclosed by a steal frame superstructure over the traveling screens and pump cubicles. The specific' areas examined-include interior

! concrete walls, floors, and ceilings; pump cubicles A, D, C, and D; and the exterior concrete walls. There was no immediate access for examining concrete at the' water line. Since this required plant

, maintenance assistance, it was arranged for the following morning.

Next, the team reviewed the exterior of Category I_ structures-I and storage tanks, including the Containment; the Cable Vault'and l Main Steam Valve House;. the Coolant Recovery Structure; the Refueling Water Storage Tank; the - Safeguards Area; the Diesel i

Gentcetor Building'; the Steam Generator.DrainsTank; the Primary Auxiliary Building; the Fuel Building; the Turbine Building; and the concrete enclosure for the Demineralir.ed Water Storage Tank (no access to confined area).

Following completion of the outside inspections, the _ team 1

. inspected the interior of the Primary Auxiliary Building and the Fuel Building on elevations 722'-6",-735'-6", 752'-6", and 768'.

Structural components reviewed included concrete floors, walls, and ceilings;-building structural steel; conduit / supports; cable tray /

supports; pipe supports; equipment supports; support anchorages; seismic gaps between buildings; tanks; masonty walls; and the spent fuel pool and fuel transfer _ canal. i l

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The walkdown resumed at 8:00 a.m., starting with the interior of the Diesel Generator Building. The concrete walls, floor, and i ceiling, the diesel generator supports, attachments to concrete, and general features were examined.

Next, the team returned to the Intake Structure to assess the condition below the operating floor; it is accessible only through normally closed manholes. Mr. Braverman accompanied the DLCo representative into the C Bay pit to check for degradation of concrete and steel.

- Following this, the team examined the Control Room, primarily

focusing on masonry wal: .s in the vicinity of safety-re' lated

. electrical cabinets and control panels.

l 3 The remainder of the walkdown encompassed the interior'of the Service Building, the Cable Vault Structure, and the Safeguards Building. The Service Building inspection included the Switchgear Rooms, the Process Rack Area, and the Air Conditioning Room on 4

elevation 713'- 6", the Cable Mezzanine on elevation 725'- 6"; and-i elevation 735'.

i The Cable Vault Structure inspection included the West Cable Vault, the Auxiliary Feedwater Pump Room, the-Main Steam Room, and

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Motor ?ontrol Center Room, and other areas on - elevations 722',

735', 751', 756' and 776'. The Safeguards Building inspection included the Hydrogen Recombiner Room, the Recirculation Spray Pump Room, the Charging Line, the Quench Spray Line, the River Water l Line, Containment Piping Penetrations, and other areas on elevations 722' and 747'.

Structural components reviewed in these areas include concrete floors, walls, ceiling, and roofs; building structural steel; .

conduit / supports; cable tray / supports; piping support anchorages; l seismic gaps between buildings;- equipment supports; -tanks; and i masonry walls. This concluded the walkdown activities' .

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During all of the walkdowns, a log was maintained, as shown in i Attachment.4, in which the team recorded for each observation the

! building / area, elevation, location, component / item, aspect

, reviewed, photograph number, and any comments. Data.were recorded for structural components where aging degradation effect were present as well as where they were not. Photographs were taken for selected items to enhance the documentation; these were noted in the log. In addition, measurements were taken when' appropriate (such as crack size), to determine the severity of _ the degradation.

In late afternoon, the audit team reviewed several LER and 10 CFR 50.59 packages related to civil / structural items. These were either selected from a list provided by DLCo during their 3

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presentation 'or were provided. by DLCo in response to specific

! questions by the audit team.

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! Throughout the audit, DLCo personnel provided responses and

! documents in-an effort to address and resolve many of the questions l_ and concerns raised _.by the audit : team during .the_ formal '

i presentation session and during the walkdowns. . The audit team then-reviewed and discussed the observations noted. A: list of the more j meaningful observations, including those that would be of benefit i to DLCo was compiled.. This list, which~is-discussed-in the next ~

j section;of this trip report, was. conveyed verbe,lly_to DLCo at the

! exit meeting held the-_next morning.

4 Result 3/ Observations t

i The exit meeting was held at'8:00 a.m. .on June 19, 1992. A

list of the attendees at- this . meeting is contained in Attachment 2.

! 'During this meeting, R. -Rothman reiterated the purpose of the

visit, which was to assess the' effects of age-related degradation i of civil engineering features,. buildings, supports'of equipment,

! . anchorages, 'and .to --determine: what type- of maintenance and-l surveillance activities are necessary, if any. In addition,-he summarized ~ the observations noted' as a result. of the formal presentation given by DLCo and' the walkdowns performed by the audit -

j team.

It should be-~noted that the - observations 1 presented .to DLCo were for. their information and do not represent requirements by_ the i

NRC. Any action the licensee may take a s ._ a result of these

observations.is considered voluntary.

! -While'most of the civil / structural-plant features examined at-l Beaver valley' Unit 1 are in very good condition-after 16' years of i operation, there were some ' components which did show varying

} degrees of _ aging degradation. - Some of' the - observations are

! discussed below, with.a more complete list and- detailed' description

presented in Attachment- 1. A f ew itemsL which were not-aging-related were also brought _to DLCo's attention _(e.g. , missing or I loose concrete: anchor bolts; one instance'of' questionable seismic i: support f or valves in a small bore, . ' safety-related p,iping run) ,

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! An examination of the exterior-condition of the containment

- structure f r o m ._ t h e ground ' and from the roof 'of ~ the adja. cent i

buildings showed _no significant signs of concrete degradation.

only minor surface cracking was . observed.- However, original

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patches L over construction-related holes are _ deteriorating-~ and

. falling out, -giving the' appearance that;small.chunksLof concrete-

i. - are - spalling. Monitoring of' this_ condition and repair 7 of f the -

,- patches -would be ' beneficial for the long1 term-integrity of1the-

containment.

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4 The Beaver Valley Unit 1 Containment is constructed of

, reinforced concrete and normally operates at sub~atmospaeric pressure (-4 psig). The quench spray and depressurization spray systems are engineered safety features designed to restore sub-atmospheric pressure conditions inside containment following the Design Basis Accident. Because the unit was in operation at the time of the audit, it was not possible to examine inside containment. OLCo presented a summary of results for all l integrated and local leak rate tests and for all structural integrity inspections conducted prior to the integrated leak rate few instances of liner bulging were previously tests. A identified; these were subsequently monitored to ensure that.the

j. deformation was not growing. Rusted areas and peeled paint in several locations in the interior steel liner were noted in some of i

the containment inspections performed prior to the ILRTs. Gouges,

anchor holes, missing concrete chunks, and some cracks in the j exterior concrete surface of the containment were also noted.

However, the containment inspection reports concluded that there i was no major or gross deteriofation of either the outer-concrete structure or inside steel liner which would affect its structural integrity.

. The last ILRT was conducted in late 1989; these tests are conducted on a 40-month cycle. The current program appears to be 1

sufficient to detect any unusual deterioration which may develop.

l For Seismic Category I structures other than Containment, cracks were observed in some reinforced concrete floors, walls, and

, ceilings. The most notable are cracks in the ceiling of the Diesel

Generator Building and the ceiling of the pump cubicles in the

, Intake Structure. The exterior wall on the South side of the i

Diesel Generator Building has a region of concrete which has spalled to a depth of 1/2 inch, exposing the steel reinforcement.

l This reinforcement shows signs of corrosion.

In the Intake Structure in the bay "C" pit, corrosion of the horizontal structural steel supports-for the raw-water line was observed. This may be due to the water that is trapped-in the horizontal structural steel shapes used to support the pipes. The i

concrete walls in this bay above the water surface appear to be in i

good condition.

a While pipe and equipment supports are generally in good

, condition, thare were a few instances of missing nuts, apparently untorqued anchor bolts, degradation of grout beneath base plates, and one case of a missing anchor bolt.

Corrosion was observed in the raw cooling water piping and steel supports for the condensing unit of'the control room air conditioning. In several other areas, corrosion was noted on piping and supports. This appears to be primarily related to

, condensation.

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A structural steel angle section, initially installed under i DLCo's IE Bulletin 80-11 program to restrain the bottom edge of a masonry wall, was found to be otly loosely. held in place. It is j important to ensure that all str2ctural modifications to masonry-a walls are maintained in accordance with the qual'.fication basis

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established in the 80-11 program. Also, any existing cracks in i masonry walls which were not considered in the 90-11 program or any cracks which may develop in the future must P4 evaluated for their impact on the current qualification basis.

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{ Photographs for some of the key observations are presented in Attachment 5.

j Although there is no formal inspection program for structures, DLCo has developed a Plant Inspection Program (NGAP 8.8). The

< purpose te this procedure is to ensure that deficiencies relating

, to materials, fire protection, safety hazards, cleanliness, j housekeeping, and radiological protection are identified and that corrective action is taken. Under material condition deficiencies, items such as rust, corrosion, loose /unbraced lines / pipes, and leaks are identified. Expansion of this program to cover other

aging degradation effects such as concrete cracks, coating i failures, and water infiltration would be very beneficial for

maintaining the structural performance of the plant.

i Another program developed by DLCo is the Settlement Monitoring Program (NEAP 2.20). This procedure provides the requirements to measure the settlement of Unit 1 and-Unit 2 structures at selected i locations throughout their operating life. This~ provides sufficient data for an engineering evaluation of the effect of settlement, as it relates to the integrity of the structures.

Settlement markers for Unit 1 'are surveyed at least annually.

This program was initiated in 1971 during construction of the plant. As a result of this program uneven settlement of - the Outfall Structure.was observed in 1973/1974. The East side settled down while the West side heaved up. DLCo used piles and steel

beams to underpin the structure to ensure no further settlement.

DLCo currently performs 10 CFR 50.59- evaluations in accordance with their Administrative Procedure 8.18-10 CFR 50.59 Evaluations, Rev. O. This procedure defines the responsibilities and requirements for preparation, review, and approval of'10 CFR 50.59 evaluations of proposed changes, tests, or experiments. Because

, this procedure - is relatively new, the 10 CFR 50 59 evaluation

! packages reviewed were in a different format. However, they did include a . safety evaluation, an unreviewed safety question determination, and a Q.A. Category Review.

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Conclusion Considering that the plant has been operating for approximately 16 years, most civil / structural plant features have-

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1 Some. structures / components, however, do show

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signs of varying levels.of aging degradation. The most severe

! cases relate _ to - concrete cracks in the ceiling of the Diesel Generator Building and the cubicles in the Intake Structure; spalling of concrete and corrosion of reinforcement on the exterior South wall of the Diesel Generator Building; the loose angle support for a masonry wall; deterioration of construction patches i

on the concrete exterior of Containment; and piping / support corrosion caused primarily by condensation.

DLCo was very responsive to the questions and obso.tations

! raised by the audit team. In one case, an excessive leak of'the service water pumps in the Intake Structure was identified by the a audit' team. DLCo immediately repaired the pump to stop the water leakage.

l The Plant Inspection Program developed bp DLCo is a valuable tool to identify material deficiencies such as rust, corrosion, loose /unbraced lines / pipes and leaks, among other items. However, o expansion of this program to formalize the inspection of structures for other aging degradation effects such as concrete cracks, l coating failures, and water infiltration would be very beneficial for maintaining the structural performance of the plant.

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LTTACHMENT 1 i

HEAVER VALLEY POWER STATION UNIT 1 I DESCRIPTION OF CIVIL / STRUCTURAL OBSERVATIONS i

Containment

1. Concrete patches over construction related holes are deteriorating and falling out. This gives the appearance.

that small chunks of concrete are spalling.

2. Based on the Containment Inspection Reports conducted prior to the ILRTs, gouges, anchor holes, missing concrete chunks, and some cracks in the exterior concrete surface were also 2

! noted. In addition, rusted areas and peeled paint in

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several locations in the interior steel liner were identified.

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3. A few instances of liner bulging were previously. identified.

DLCo stated that these were subsequently monitored to ensure that the deformations were not growing.

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4. Corrosion of the containment penetration for the component

cooling line was observed from the Safeguards Structure at elevation 722 ft.

j Intake Structurg l

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1. Concrete cracks in the ceilings of the pump cubicles were identified. Many of the cracks were located near the access panels used for pump maintenance.- Crack sizes up to approximately .075 inches were observed.

2. Corrosion of the horizontal structural steel supports for the raw water piping was observed;in bay "C" pit (below grade). This may be due to the water 1that is trapped in the

' horizontal structural shapes used to support the pipes.

3. In some-of the pump cubicles, grout-degradation and.

baseplate corrosion were identified in small diameter piping.

supports. In addition, conduit supports on the concrete wall had missing washers, untorqued anchors, one missing anchor, gaps with the wall and bent members.

4. Three vertical cracks were observed on the exterior concrete wall on the South side. The cracks were approximately 02 inches wide and 10 feet long.

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piesel Genera' tor Buildina

1. Long cracks running in the ceiling of both Diesel Generator j Rooms were observed. The cracks run the entire width of the room from the East wall to the West wall.

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, 2. The exterior South wall has a-region of concrete which has spalled off to a depth of 1/2. inch, exposing the steel I reinforcement. The reinforcement shows signs of corrosion.

l Prinary Auxiliary Buildino e

i 1.. A. structural steel angle, initially installed under DLCo's j IE Bulletin 80-11 program to restrain the bottom edge of a j masonry wall, was found to be only loosely held in plac'e.

1 The masonry wall where this was located is at elevation 722 ft.- 6 in. in the Cable Vault Structure. In addition, a vertical angle did not have an anchor at the top and no i washers were present at other anchors where oversized holes I

were used in the angle.

2. At elevation 722 ft.-6 in, a long, large crack in the concrete ceiling was observed. Signs of rust discoloration were also present.

3. Corrosion was observed in the raw cooling water piping-and steel supports for the condensing unit of the control room i air conditioning. This was identified at elevation 722 ft.-

+ 6 in, i

j 4. At elevation 735 ft.-6 in. grout degradation was observed below the baseplate support to the CCR heat exchanger 1A i pressure gauge.

. Service Buildina .

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1. At elevations 713 ft.-6 in, and 725 ft.-6 in., the concrete ceilings exhibited signs of water infiltration and calcium formation.

2. Degradation of the foundation and corrosion of steel supports were observed in the Switchgear Room, elevation 713

, ft.-6 in.

b 3. Cracks in the masonry wall next to the computer room at elevation 735 ft. of the Control Room were identified.

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Cable Vault Structure l 1. Cracks were identified in-the masonry wall on elevation 735 i ft. of the West Cable Vault.

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l 2. Water fr'om.the fan coil unit drain line at elevation 735 ft.

was corroding the base / steel supports.

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3. Corrosion of the structural steel frame supporting the main 3

steam and feedwater piping was observed at elevation 762-4 ft.-roof level.

Safeauards Structure

1. Corrosion of the sliding support plato: for the river' water

! piping was observed at elevation 722 ft.

i j 2.. Corrosien of two pipe support base plates was identified.on l.

the ceiling above elevation 722 ft.

! 3. Water infiltration and corrosion of steel angles at the

ceiling, adjacent to the exterior containment wall, was i observed at elevation 747 ft.

4 Other Structures

! 1. Steam Generator Drain Tank - cracks, water infiltration and

calcium formation was observed at-the West wall.

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. ATTACHMENT 3 )

YV k4 7 y Ducuesne Licfr: Com3any" i

i Beaver Val ey Power S:a: ion i

Unit 1 I

l N lC AUDIT i

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l June 5, 9 9 2 ~: 7ru June 9,1992

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ENGINEERING PRESFETATION AGENDA Tuesday, June 16 (All Day)

SUBJECT SPEAKER-Design Criteria Including V. Hvang Seismic, Vind, And Missiles Design Codes and Standards Containment Testing J. Patterson and Surveillance Support Anchorage Issues T. Vestbrook Spent Fuel Pool and Spent G. Ritz Fuel Storage Racks Intake Structure C. Mancuso Masonry Valls G. Ritz Corrosion Protection T. Vestbrook Geology, Foundation conditions, T. Vestbrook and Ground Vater Flood and Dam Failure T. Vestbrook Buried Piping Integrity ' '

C. Mancuso 0A Category I Structures C. Mancuso-Inspection and Surveillance Programs Settlement of E. Ebeck Structures and Verticality i

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l SPEAKER SUBJECT J. Nazar Seismic Instrumentation C. Mancuso Safety Related Storage Tanks C. Mancuso Civil / Structural LERS B. Sepelak Past Dispositions of Structural Issues Identified in Past NRC Inspection Reports T. Sockaci Civil / Structural 10CFR50.59 Evaluations Plant Safety Procedures - C. Mancuso Abnormal Operating F Scedures Summary of Planned Activities B. Sepelak For Future License Reneval USI A-46 Resolution G. Ritz IPEEE Summary S. Nass NOTE: AGENDA MAY BE REARRANGED AS REQUIRED.

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. GENERAL DESIGN CRITERIA

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. Codes and Standards--AISC specifications for steel construction dated 2/12/1969 for older structures and dated 11/1/1978 for newer structures.

ACI building code requirements (ACI 318-63) dated 6/1963 for older structures and ACI 318-77 dated 12/1977 for newer structures.

. Stress criteria for loading combinations of Category I structures other than containment:

D.L. + L.L. <fa (ste'el), fc (concrete)

D.L.+L.L.+0BE <1.33*fa (steel),1.33*fc (concrete)

D.L. + L.L. + SS E <0.9*fy (steel),1.5*fc (concrete) u D.L. + L.L. +W <1.33*fa (steel),1.33*fc (concrete)

D.L.+ L.L. +TO R <0.9*fy (steel),1.667*fe (concrete)

D.L. + L.L. + F1 <0.9*fy (steel),1.5*fc (concrete)

D.L. + L.L. + F2 <1.33*fa (steel),1.33*fc (concrete)

~~

.SA ISMIC DES4;iN CRITERIA -

o

?, ,.

. Site specific ground design spectra-0.06g OBE,0.125g SSE

. Vertical spectra taken as 2/3 of horizontal

. Soil-Structure interaction in the development of in-structure floor response spectra-Unit 1 spectra submit',ed on Docket NO. 50-334

. Damping values conservative in comparison with REG. GUIDE 1.60

. Method of analysis

1. Static analysis-Simple structures

. Flexible structures-Static load factor of 1.3 multiplies peak acceleration of in-structure floor response spectra and total weight of structure applied at the center of gravity in horizontal and vertical directions

. Rigid structures-Rigid range response acceleration multiplies the total weight of structure applied at the center of gravh/ in horizontal and vertical directions.

2. Dynamic analysis-Response spectrum method is mostly used. Structure ,

is modelfed with sufficient mass points. The normal mode natural frequencies, eigenvectors and parucipation factors of the undamped structure are calculated. The model accelerations of each mode is obtained by scalling the in-structure floor response spectra of appro-priate damping using natural frequency of each mode. Modal forces of each mode are calculated by multiplying the mass with the modal acceleration, eigenvector and participation factor ar.d applied at :

the mass points of the mathematical model of the dructure. The modal responses are combined with the guidelines of REG. GUIDE 1.92.

s e -.

o

-stjillll:Ht!"illIllllIli I l l l l 1 gyt.]ItHjlllllllifllli 1 .alll 1l tryttujntllittijittfltIil l f f i 1 l

s. . e . .. . . . . . ._..

...-,4.. s. . .

Pfalco t$tCS*

klll . x(h(%N lh??r?? ?h $ emk ^,N/?X"&D$E0 e x a,ms' zur n amu uc x aa hAwsu NN% // / / N A /\ TA \V A

////N AA N'S\ \\%/<// N A N \'2PW//'X/\ X \ !

W// X /\ X %)2?W//X/\/\X \ MSSW_ / /\ /\-\

W/ /\ /N'\ MS$W/ /\ MD , . . . .

18)ZdM'/X MM /\ M)C(M

/\ 8@Of , , ,

Dh As2@Mk A(8@Mk Af8@

s lkhh!Nk

=_mm,=a w khh!bn su

,<=u .. ^=^ <

hhkk$b....

a wsw

,.. <<u r xAWwNN%W n am mn, M W/s WN\M////N A /\ hA\ \\M ,,,

,,,,, //// N /N X \22W// X _/\ X \'*22 W// X/M%%WM// )4)N \ ,,,

3 ,,,

j ... W/ / WAG',

ML/s/MA\M$$W/

XEMVNMM30dM;/\

/\ /\\ M%$

'83Z(

MFAW ,

MYMI8@MxM N@@b Mk2@

j ,..

MRhh!?L_la_hE

,==

@Bs ;#$!?S ..

m =m u- An x ve,nw m e a <\ '5A ^ wA-wu , A n a wsu A VSh , ,,. . ,

A hA \%%//// N A /N r V kNMG'//N /N

.., 7//N /S X \ NVs!

X/\ X \ \ '22W// X _/% X \ 2W/ / 'X/\ \ ,,,

8/// /\ \MD W/ /\ /\ \ M95W/ /t /s \ M$$W/ /\ ..,

M ' N 183ZdMK /N 8)Z(MW/\MMR ..,

Mk2@Nb Mk2@M'\ Mkk@

Nb ..,

k Mhk b$ ,.

.., x khbkNk h h h ! )

FREQUttiCY (CP18

9 FIGURE 2 RESPONSE SPECTRA 0.06G OBE BEVER VALLEY POWER STATION UNIT 1

E ,

n

. WIND DESIGN CRITERIA. .

~

. Extreme wind velocity of 130 MPH (Including 1.3 shape factor) 100 yr. inter /al wind storm per ASCE paper 3269.

. Tornado wind velocity of total 360 MPH--300 MPH rotational and 60 MPH translational.

. Differential pressJre of 3.0 psi in 3.0 seconds.

. Wind loads calculated per ASCE paper 3269.

i

. FLOOD DESIGN CRITEERIA ..

l

. Location: near Ohio River (normal pool: El. 664.5 ft) l l

l . Probable maximum flood up to elevation 730 ft-0 in. :

l The flood load due to the buoyancy and hydrostatic ,

i pressure associated with this flood level is designa-l ted as F1

. Standard project flood up to elevation 705.0 ft :

The flood load due to the buoyancy and hydrostatic pressure associated with this flood level is designa-ted as F2 i

i, -. . . _ - . _ _ .._ - _ . - . .

CONTAINMENT STRUCTURE i BVPS UNIT 1 j g %

's

. N i a

\

f 1/2 "

N} )

,/

2 1/2' j fj R-63' 9. ;

,- \ .

) i 2

i Sprina j I "i \

\

~~ ~

l.ine /

s i

~ ~ 3/8" l

1/ 2' 185' f ~ Steel Liner

! Ground -Reinforced Concrete j Elev. 735' . ,

.;trument Pit 4-r 1/16" Waterproof 1/4" Membrane 10' P " 692'11" Reinforced Concrete p e i n l

12" Reinforced Concrete 4" 3/32" .

} v i ,

' Porous Concrete n i 4

_. . . , , . -w ., . ,. , --

y

l CONTAINMENT PENETRATIONS l

l TOTAL PIPING PENETRATIONS 112 1

l i PENETRATIONS TESTED WITH AIR 54 i

PENETRATIONS TESTED WITH WATER 14 l

PENETRATIONS NOT SUBJECT TO LEAK RATE TESTING 21 i

i SPARE PENETRATIONS 23

! I j i i TOTAL ELECTRICAL PENETRATIONS 109 4

i.

PERSONNEL AIRLOCK !

l EQUIPMENT HATCH i

EMERGENCY AIRLOCK !

i b

I i

i 3

l

CONTAINMENT INTEGRATED LEAK RATE TEST;

HISTORY FOR BVPS UNIT #1

^

NOVEMBER 3 THRU 23,1978 ~ FIRST ILRT I

NOVEMBER 3,1978 TEST COMMENCED.

]

NOVDiBER 4,1978 TEST PRESSURE OBTAINED.

NOVEMBER 5,1978 LEAKAGE DETECTED AT CONTAINMENTi t VACUUM AIR EJECTOR PENETRATION AND TEMPERATURE FLUCTUATION CAUSED BY 'HE DATA ACQOISITION

EQUIPMENT.

NOVEMBER 19, 1978 REPRESSURIZATION OF CONTAINMENT

. COMPLETED FOLLOWING REPAIR OF THE CONTAINMENT VACUUM AIR

EJECTOR PENETRATION AND THE DATA ACQUISITION EQUIPMENT.

3 NOVEMBER 21, 1978 24 HOUR DATA ACQUISITION

COMPLETED AND LEAKAGE IS WITHIN -

ACCEPTABLE LIMITS (0.0406% / DAY).f NOVEMBER 23, 1978 SUPERIMPOSED LEAKAGE VERIFICATION TEST SUCCESSFULLY ,

i COMPLETED AND CONTAINMENT i DEPRESSURIZED TO ATMOSPHERIC

PRESSURE.

4 9 d

i G

,~ - , . -- , e , .,.

i l i ,

CONTAINMENT INTEGRATED LEAK RATE TEST l l

HISTORY FOR BVPS UNIT #1 JULY 30 THRU AUGUST 3,1986 THIRD ILRT JULY 30,1986 TEST COMMENCED.

j JULY 30.1986 TEST PRESSURE OBTAINED. !

JULY 31,1986 TEMPERATURE FLUCTURATION DUE TO j CHANGES IN THE CHILLED WATER l TEMPERATURE TO THE CONTAINMENT AIR j RECIRCULATION FANS.

I AUGUST 1,1986 CONTAINMENT AIR RECIRCULATION FANS ISOLATED.

. AUGUST 2,1986 Co.NTAINMENT AIR TEMPERATURE l

STABILIZED AND DATA ACQUISITION RESTARTED.

AUGUST 2,1986 DATA ACQUISITION COMPLETED (BN-TOP-1 METHOD) AND LEAKAGE IS WITHIN ACCEPTABLE LIM!TS (0.0143 % / DAY).

AUGUST 3,1986 SUPERIMPOSED LEAKAGE VERIFICATION TEST SUCCESSFULLY COMPLETED AND CONTAINMENT DEPRESSURIZED TO ATMOSPHERIC PRESSURE.

4 a

2 4

9

l CONTAINMENT LOCAL LEAK RATE TEST !

4 HISTORY FOR BVPS UNIT #1 1

i AUGUST 7,1975 PREOPERATIONAL LLRT 903.11 SCF/D l

1 FEBRUARY 28, 1977 NORMAL SURVEILLANCE 2628.62 SCF/D l

NOVEMBER 18, 1978 NORMAL SURVEILLANCE 1712.13 SCF/D 1

SEPTEMBER 12, 1980 FIRST REFUELING OUTAGE 3722.98 SCF/D.-

MAY 25,1982 SECOND REFUELING OUTAGE 3400.53 SCF/D SEPTEMBER 13, 1983 T!'RD REFUELING OUTAGE 2458.96 SCF/D l

j DECEMBER 15, 1984 FOURTH REFUELIMC OUTAGE 2007.35 SCF/D AUGUST 8,1986 FIFTH REFUELING OUTAGE 1548.28 SCF/D FEBRUARY 8,1988 SIXTH REFUELING OUTAGE 929.31 SCF/D 4

4 DECEMBER 8,1989 SEVENTH REFUELING OUTAGE 1052.67 SCF/D APRIL 15,1991 EIGHTH REFUELING OUTAGE 871.73 SCF/D ACCEPTANCE CRITERIA 3929 SCF/D OR 0.6 La

, , ,y ,.,, .,- , + ,m

e - . i l

VERIFICATION OF STRUCTURAL INTEGRITY OF THE CONTAINMENT LINER AND CONCRETE STRUCTURE. FOR BVPS UNIT #1 NOVEMBER 1978 CONTAINMENT INSPECTION PRIOR j TO THE FIRST ILRT RESULTS: THE INSPECTION OF THE REACTOR 1 CONTAINMENT STRUCTURE REVEALED NO MAJOR OR _ GROSS DETERIORATION OF EITHER THE OUTER CONCRETE STRUCTURE OF INSIDE -

STEEL LINER WHICH WOULD AFFECT ITS-STRUCTURAL INTEGRITY.

ABNORMALITIES: 1. NUMEROUS SURFACE BLEMISHES I AND GOUGES IN THE EXTERIOR

. CONCRETE SURFACE.

2. BULGES AND WARPAGE IN THE

INTERIOR STEEL LINER. ;

_3. PAINT PEELED OFF OF SEVERAL LOCATIONS IN THE INTERIOR -

STEEL LINER.

l .

j-l-

l' i

s i

I-,#.-mc,,.,v-s , . , , .-,,,,-.-.,,....,,=--,.r#wn.,w.. e.,.-%w w . , - - , ..-.,e,e.<, - .w,--,.w.- , v -- w-4.... - , ..

J. .

i 1 8 ~

l l VERIFICATION OF STRUCTURAL INTEGRITY !

! l OF THE CONTAINMENT LINER AND CONCRETE l

i STRUCTURE FOR BVPS UNIT #1 s.

i JULY 1986 CONTAINMENT INSPECTION PRIOR TO THE I

{ THIRD ILRT

! RESULTS: THE INSPECTION OF THE REACTOR -

1

CONTAINMENT STRUCTURE REVEALED NO i

j MAJOR OR GROSS DETERIORATION OF EITHER i THE OUTER CONCRETE STRUCTURE OR INSIDE '

i STEEL LINER WHICH WOULD AFFECT ITS l

j STRUCTURAL INTEGRITY.

( ABNORMALITIES: 1. TWO ADDITIONAL GOUGES NOTED ,

IN THE EXTERIOR CONCRETE i SURFACE. ;

! 2. PAINT PEELED OFF OF LOCATIONS l IN THE INTERIOR. STEEL LINER.

b

i

-1

- 1 l

I L

1 j ..

..-,,,_._-.m ,. - . , ,

.,,,,,Lr.- i, , . ,/3 '. - . ' .: - - ,....__..~..,_,,.._...._..,,,,z..

- ,..,--,,,.. .. :.,...~ . .

e i

i .

.m .

' .~

. SUPPORT ANCHORAGES, ..

l ...

l

- Design Criteria & Prac: Ice 1

}

- IEB 79-02 Reso ution i

- u,tler Lssues j I

I I , .

! +

4 l

i i +

i

SUPPORT ANGiHORdGES .

d 6

- Desig n Cri':eria & 3rac': ice (con'":}

A sa"ety fac1:or o" L is usec for cesig n For Hi':i oo':s, a caraob ic slear-

~:ension in':erac": ion formula is used. A s":raig 7t ine in":eraction

, is usec for Maxibo ts Site S":anc ard covers ins':aia": ion and ins aec": ion requiremen~:s 1or ex3ansion anclors

I i .

I SUPPORTANCHORAGES " .

79-02 Reso u: ion l

I i

A samaling 3rocram was .

3erormec "or anclors associa':ec l

! wi':1 ~:le 28 sys: ems in 79-02 sco oe Ma'ori:y o" anchors were she :yae Re3 airs or moci"ications aer ormec

!or c e"icien': anclors Su a cor~s at: ached to b oc<

f walls were removec. or mocifiec Fina Reaort issuec Ju y 7, 980 l

5 v v ~* - e e we-vv, -* ,rs un=,

I' l -

SUPPORT ANCHORAGES 0: 1er issues (con't) l IE \186 !

Reviewec a. Daseo a:es in l 79-02 scoDe l

Sma numoer used /2" Q l i

! Kwi'< Bolts Recucec a owao es cic not a=ect de.sig n margin (F.S. >z.} ,

i I

! Onsi':e :ests ma":chec' Hilti's i i origina ul":ima"e values l j

! l

Revised allowaale loads i

, l l l 1 .

SUPPORT ANCHORAGES O":ler Issues (con':)

EN 88-25 (con':)

i

- Onsi:e shear :es':ing o" H <B-Il veri"ied ec ge cistance o" 12 anclor ciameters

-i+i Par: 21 {Jan.1991} on recucec caoabi ities "or 1" anc 3/4" anclors Site saeci"ic :es:s me':

or exceec ecl Hi' :i's u :imate loac.s 9

-.-,w-en.-,e---vewvym,e----we-w-e--e-,wy,m--.-,emper,-,.e-wem-

2I l SPENTFUEL PQOL & .

i "

i L

STORAGE F1AC'KS

\

S:ruo:ure i

l l - Desicn Fea:ures l - Rac< Clang es l -

i 1

l .

4

4 i e' (

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=

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2-23

. . - - . - ~ -. - _ , . - _ _ - + _s

i

l 1

1, J

r I

Table 2.2.3 i J COMMON MODUI,I DATA 1,

l - ,

l storage cell inside dimensions- 8.75 irach i dimension (nominal):

t 4 Storage cell height 166 inch-(above the basaplate): -

0.75 inch Baseplate th!.ekness:

1 Support leg height: 5-1/4 inch (nominal) l Remotsly-adjustable legs

' support leg types with lateral gussets.

i . Number of support legs: 4 (minimum)

Remote lifting and -

' handling provision Yes t

Boral i

t Poison material:

Poison length: 144 inch

- Poison vidth: ' 7.5 inch 10.82 inch (Region I) -

Call Pitch: 9.05 inch (Region II) ,

0 i

e 2-16

,i 4

4 4 - p g..- p ..,, , ...-w --....r,, , , , , , , n. a w e, , , , , n,y, -7,e e . .e,, - , , - , , .w.s y

e 4 M.* K-W q l.-

. 'd g,1 1 f *,e eS '.*

L.: T4

~ %J C

~

h s, ,*

st i

=

U

.o At g h N{

e f.s JI :n I- #

ac JI 2

< O n 1 y

=

,f

~

m a E

d ,

a

, ,= 0 y .

C F. ;

M b '

b

= <b

.,2 ac <

b a 9-bC , =

C 0

, s. p C 7 < E U

, a *

C N

E s Q

> s E [ >f s s ,. s v'

y Q f

n

=

M Q

rs k C s W '

88

= % %a L QC e ,

A W

- g - o N

2 3 - '

f"$

C m C

. w o

u a m ) .

I

== - c: - -

0 0 %

C l 0 t.: -U y ,

b g x >

E; [j . .

5 E N.

m

.

D.8 Q 8 C 6

v Y

Y $

L r 1

, w-3-11 l

4 .

~

.f N -t i s M. r r

_ ,1 d $ d h q b N .

> d p 4 18

\ /_ 4 sm i <r, _qr % r -

d i h- d f lW N i # 4 k li N

- /, A m ,

s , , , 12 r r ,

il b'~ sg In d ll 4 h Q v 4 l'

' ' I, -\ J 2 /. \'

' " I - twr N , '" ( ,

1 < > 'I n l' o

< v - < L L i_ x 1- '

- e 1 m -x

+- ,

d b d b d p 1

1 4 ' '

9

$ - ll >

+ r- 1 i i ., .i FIGURE 3.3.2 ARRAY OF REGION 11 CELLS (NON-FLUX' TRAP CONSTRUCTION) 1 3-15 s e

I 1 '

O

~

RERACKING EFF5 CTS Original Current Proposed Backs:

i Fuel Assemblies: 5. 5

3. 5 Endchment 49 " 7*7 ' "

No. per Rack 16 = 4x4 832 1625 272 Total 1222K 2,384K 380K wt.

SFP/Buliding:

149 F 153.4 F WaterTemp (125 F)

(Ftc Core Offload) 15,367K Total Bldg.WL 15,181K 12.7 ksf e - e.

Soll Prassure 11.41 ksi No No ,

Structural Design I Modification

r. .

INTAKE STRUCTURE i

Overview I -

l Common S:ruc~:ure 1

I I

Key Equi 3 men ~:

l

) Layou:

i l

i Surveil'ance ,

l O'Jera":ing Surveil ance Test

, l l

j l

Frecuency ,

l Ins aection o" Bays c uring drain ,

cown I !

i

> .. _., _ , _--, _.- ......-., _ _.,-- .. ,. . w

t

.:-@ w. s- @~' w.;~ @ w.c @ e, . e @

yv it f.

' .-r' ra,,. eg &l c s $e t 4gf

) ' 2 i

T. %a. e M

?

A@ :q' , q 4, ,

.:4$. :( ~

... *Y l,y

._,, f~ Qii , - , - $

t-

g fn'' n'; , ) pi s;.s;p n s.. v. e - s.e ;s

~ '

-~ '

[p. !}I 1 ii'!.-NhMl--~~~~

f- ~ 7 N c- ~ ~ ~fk- "' M. . . s~m? "" >

dl

{} ggq13,$ % .. m

.r,.-

1u l, l!ll 8

L L Dji . j. .j i dj ;

.,qsp s17[1 m m-4 i .,! -

og m w Lljvp).s, v.jik , . . .

B t 4

re g

i g .m : i .... - ...-- .

e.

[ . ,

4 . ,

N.4:$i. .

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t. ._

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.- :.p -

,, ,u ,-n,. -

o l'

l -

rg ej e .'amJi 1 2 4 yy, i 3 i

.e dnga l++ l iT..

r i.1, h5!.IY11 =I ;i .b Y i- -i _ s dbjgdb.

4

! l E,

... .m . y a

4n$h- v u m- m

.u -

e j! .n Ylk!o4. . , l!wilbp'd $a h h wll .

d sg a,g!ph"y,y ! y!!h 2 Lai R,4;

-d ,Jal;ib l iam g a -

n.t r., .

- -4 ,2 ;

c1E!"%;3 s- .

0

!, i A ch- #

w..ar E1

1. 'y f Wl rti.qlla

.1 .i

$>1.,13 [ d, [6u

{ h- J l5!).i[M

( >I ;f t j!

-mi u ,

, i l i, u g k:n,'1].4

, 4 5' 4

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.%m c; 9' l l

= 'x {

"i6

. 1

[ v s.

c g

! ! l A f-

!l

- ls .)=;p r - t . n!.. e!_ y +[,).- -J sn r

i

, s1 -

i 3

Q..--fmlL-[__.;,17. '[j T ' Iqn', )

w .i f 4. if g. i j f h il t ;

.-- .- e Eh l -l ,

h.M , .l..u.U:dil I:3b ' ll< h n {l()$$gi !h Ifi 7 m u

w.c n. f, ti,M -

e .....

t 70 g of CA As*4. tab

i i lNTAKESTRUCTURE a ,

)

~

l i

I i !

00serva: ions . l l

l

No Jegraca: ion i t

I Wa":er in-Lea <ac e During i

Drain Down

(

I l

I

I l

l

~

l I

c __ _ _ _ __ _ _ ______ __-___-__

1-l C6ACRETE i3 LOCK WALLSj .

L IB 80-11 / IN 87-67.

'"'f I

lEB 80-11:

L

Resulted in 108 Walls Considered; 105 Governed l

l by 80-11 Criteria & Reviewed; PAB (65), CV (9),

! FB (2), SB (29) i 4 Were 79-02 Walls With >21/2 in. Dia. Piping

15 Did Not Meet Our Acceptance Criteria-f

! No TS Equip l

11 Modified - Equip Removed, Walls Braced /. :

l Stiffened with Structural Tube Steel (DCP-424) l l Walls were Field inspected & Sketched by DLC; l Analyzed by S&W (Procedures BV-1-8011-01 l thru 05)

CONGRhiE BLOCK WALLS l ..

IB 80-11/IN 87-67 '

^

l

.[-

i in 87-67: .

L Our Review Concluded IEB 80-11 Effort was Acceptable (EM 36624):

I l l

- Materials were Controlled Per Spec BVS-346 l and Field O/C, Samples of Documentation

Furnished to NRC as Attachments to Reports

- Procedures were in Effect - Walkdown /

Inspection, Evaluation Criteria, Detailed r

Analysis Methods l

l l

- Simple, Defendable Edge Assumptions Used i (ie, No Ties to Structure Assumed which

Require Opening Wall to Confirm)

\

1 i

i _ _. . _ _ _ _ _ _ _ _ __. _ _ ___ ____ __ _ _ _ _ _ _ _ _ _

CONCRETE BLOCK WALLS . .

1B 80-117 IN 87-67

. p - '

s l

i l

l Bldg-!nduced Strains and Thermal included;

! No Wind, Tornado, Missile, Pipe Whip / Jet '

1 Impingement Walls i

I l Professional Photographs Taken of All Walls l

NRC TER Approving DLC Report Received l 7/16/82 l

l l

I .

i 1

k l

\ :

i

! /

' DNCRETE BLOC'K WALLS i

~IB 80-11/ IN 87-67 ~

f

~

- Performed Wall Inspections and Identified Any i

Additional / Deleted Equipment, Damage', Cracks, Devicitions from Drawing (73 Walls)

- Evaluated Changes Using 80-11 Criteria; Most Actual Changes were so Mir,or (eg, Fire l Extinguisher, Small Conduit / Tubing, Chipped :

Block, Small Corings) That 25 psf or Judgement Controlled. However, One Wall had Courses l

Removed, Another (without equipment on it) l had Steel Framing Substituted for Bottom !

Courses Under a DCP (480) -

i

- All Walls were Still Adequate, No Modifications Made

- Next Inspection would Occur 1999 per NGAP 8.12, Although Option Exists to inspect in'1993

I

l j

CORROSION.PRdTECTloN.

o

Pro:ec:ive Coa:ings l

! :n~:erior Structures l

l

- Ex:erior Ex30sure 1

- 3e ow Grounc i

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Wateraroof Niemoranes i

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-CORROSION PROTECTION

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- Vlost common y used sys: ems l l are al<ycs or urethane toacoat l over vanous 3 rimers l t Be ow Grounc/ Immersion i

- Coa Tar !Ecoxies Speci"iecL

) - Linings not used l

l

- Vlalori"y o" :an'Ks are Stain ess s:ee l

Coatings have aer ormed well l in service l Wa":erproo" IV em 3ranes k

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3 L FLOODS AND DAM FAILURE . . .

- Highest Historical Flood March 1936 703.ift. Prior to flood control reservoirs Decernber 1942 692.9 ft. Flood control June 1972 692.7 ft. Flood control (current)

- - Plant is shut down when river level reaches 695 feet.

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. 3.

FLOODS AND DAM FAILURE .

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F ooc Pro:ec: ion (con'":}

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In":ernal Insaection l

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ASTM A' 06 Grace B Carbon S: eel l 1

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03 era:ional Surveillance Tes:s i

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03 era:es at A':mosaheric Pressure l

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O CATEdbRY I STRUCTURES l .

! 7 Inspectio.n & Surveillance Progrhrris l

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I l Qua i"y Services Inspec': ion Procec ures

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Examina: ion lec,uirements l

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L _ _ - . ___._ _ . . . _ _ _ _ _ _ . _ _ . _ _ _ _ _ . _ _ . _ . _ _ _ _ _ . . . _ . . _

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l SEISMIC INSTRUMENTATION

' ~

./ .

Linit #1 Strong Motion Recording Accelerograph a Peak Shock Annunciator and Recorder Non-Annunciating Peak Shock Recorders

Peak Recording Accelerometers to be Mounted on Equipment

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' Unit #2 l .

Strong Motion Recording Accelerograph l l l l

Peak Shock Annunciator and Recorder l

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b 1971 1979' 19 81 1993 1985 1987 1787 /T?/

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f St-I I LEMENTOF STRUCTURES

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l Unanticipa:ec se::emen:s and !

l encineerinc cisaosi: ions i

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l Status o Unit settlement l l

orog ram as of 12/1991 .

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Set: emerr: mar <ers indica:ec:

l East Sic e Set: emerr: v West Sice Feave A Solu: ion: En":irely unc eroin the l

l s':ructure ~:o ensure no "urtler set: ement i Four (L} HP 3i es c riven to re"usal .

! anc two {2} wide f' .. ige s:ee

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! SEPARATION OF STRUCTURES.

ANDVE RTICALITY.. .

.~ .

1 S":one and Weas~:er Struc~:ura .

i Desic n Cri~:eria (BV VI-52) "or l Sha<es oaces'is four (L) incles.

! S1a<esaace Loca: ion Plan n

l 08700-RC-18A.

Re a':ive cis'a acemen": pro"i'es are par: of Structural Design Cri":eria.

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Four {L} incles o""ree space is j c rea"':er ~:han ~:he max builcing disp acemen": ay a factor of 2.

I i.______-___________________

v . .

~

SAFETY RELA ED ~

STOFlAGE TAI)lKS .

i : .

l

ASME XI Program l

Tan < Leakage & Corrosion l

l Settlement .

i -

Tan < Appurtenances-Foundation i

4 i _ _ _ . . . .._.. _ __. _ _ _ _ _ _ _ _ __ __ _ _____ _ _ _ _ _ _ _ ___

~

f LICENSEEhENT REPQRTS '

. 'B.VPS # 1 1 l

LE l 1-76-053 Sloc< Annuncia:or Ino 3erab e LER 1 10- Pea < Shoc<

Recorc er O.O.S.

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LE R 028 Failure o" Seismic Vlonitor Recorc er

LER 1-78-040 Misa.igned Reec l

l Switcles on Pea <

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! Shoc< Annunciator l

i i

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LICENSEEEVENT REPORTS l .,

BVPS # 1 l

l LE 1 037 F awec. We cl in i l Con:ainmen: Liner

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LER 082 Possia e F.oor l

Overload in PAB l

l LER 0~ 3 Con:ainment Liner !

t l Bu ge anc Vlissing l

Liner Test Clanne P ug l l

LER 017- Void in Containmen":

! Wa Near Ecujomen":

match

4 j<..

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i :

! PAST NRC INSPECTION '

i STRbdTURAL ISSUES

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~-. ,;.-5 : ,

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8earC1 O' Cata3aSe '

! icenti'lec ~:le fo ow'nc i

items:

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IF 80-12-01 .

U \R 8 06 U NR 80-27-30 l UNR 82-08-03 UNR 83-2' -02 .

U NR 82-11-03 UNR 87-11-02 f

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PASTNhiQ JNPECTION '

STRUQTDl%lSSW~" ::

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,i ', ; -

INSPECTOR rdLLOW .TEV 80 2-01 NRC to review DLC Ac': ions Concerning Cons:ruc': ion Deficiencies in Sa"e":y-Re a":ed Tan <s ,

~:em reviewec in ce3:1in Ins 3ection 80 ~'7

em c'osec in Ins 3ec": ion 80-25 4

4

i.

l

. .3 l

.. . .. RAST N..FIC INSPGCTION. .

STRUCTURALISSUES'~

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~ '

j . . .

l L'N RESOLVED ITEM 81-2.0-06 ,

I l 1

Review Uni'; 2 S":ruc':ura Desic n l .Je"iciencies for A3o icaality :o l Unit - (CON'T)

I l

l 1

em reviewec in .nsoection 8~ -25 ;

l l

l':em reviewec and c osec in i

Insoec": ion 83 ~ 9 '

t L .._.... _ .- .. _ .. _ ....._. _ . _ _ ..._...

l ITEMS REL TED TO

.- BU:LLETIN 79-14~~ . -

l i .

_.. ...y.,.....

i I Uh ~1ESOLVED TEVI 82-08-03 l l Seismic Desic n De"iciencies ,

i

(

l QA Audit veri"iec acherence :o ,

IEB 79-14 l

Sam a e o" wor < 3ackages l inc e 3 enc ently veri" led l

l Ac': ions reviewec in .nsaections 82 ~ 0 anc. 83-19

L:em o osed in Inspection 85-06

~

i

PAST NRC INSPECTION STRUCTURAIJISSUES U NRESO_VED TEM 82-11-03 Review Accea:abii:y o" Con:ainmen:

Liner 3u ges (LER 82-13}

Lns'3ec": ion orogram of con":ainmen": iner ou ges ini":ia":ec (BVT .3 ' .47.6)

~

I:em~ reviewed anc closed in Ins 3ection 83-25

i.

j . ,

l .

i PAST NRC INSPECTION-

! STRUCTURALISSUES .

i l

l L N lESO _VED ITEVI 83-21-0' I

Provide Summary Report to NRC l

recarcing Anolor Bo t Sti= ness

<<Re": EB 79-02)

!

Summary Reaor: Suarni~::ed 9/84 i

i "em reviewed ancL closec in ins Dec: ion 85 ' 7 R

a

' ~

PAST NRC INSPECTION STRUCTURAL ISSUES . ..

D EV ATION 86-06-03 EDG Fue Oi Day Tan <s Sua3or:

Craccles were not oui':~:o Incus:ry Coc es a33 icable ~:o Seismic S:ructures DC 3 739 re a acec su a aor:s "or "uel oi c ay tan <s

~:em reviewec anc c.osec in Ins'Jec": ion 86 '

~

o l

~

l d

, 10 UFR 50.5.9 EVAll)AIlONS-Design Change Evaluation Summary Package No. Sub,iect BV-1 Cooling Twr QA Category 111 161 Roadway Slope (OSC Mtg. 81-80,7/2/80)

Protection BV-1 Emerg. Airlock EAL, Blank Flange Conn, l 210 Installation Missile Shield and Concrete Access Platform are OA Category I, Seismic.

Rest is OA Cat.111, Seismic t

l BV-1 New Rx Cavity OA Category til 216 (OSC Mtg. 7/25/78)

Seal 1

1

~

10 CFR 50~.59 EVAh. hATIONS Design Change

~

Subject Evaluation Summary Package No.

Upgrade Peak Shock OA Category 111, 397 Recorder Seismic OA Category I t

424 Concrete Block Modifications for IEB 80-11 .

l l

OA Category i I Concrete Block Wal!

480 Modification to Allow Removal of LW-E-4 Concrete Block Wall OA Category !!!,

481 Modification to Allow Seismic Removal of LW-E-1 l

I

i

,t

< f 10 CFR 50.59 EVA UATIONSO. .

j i

l Design Change Package No. Subject Evaiuation Summary

! i

! 706 Refueling Pool Cofferdam QA Category ll,

Seismic l

(

723 Replacement of Containment QA Category ill, Concrete Floor Plugs with Non-Seismic l

! Grating 735 Replace Defective Metal QA Category 111, Inserts in Missile Shields Seismic

. and Floor Plugs 4

739 Replace EDG Day Tank QA Category I, Supports Seismic

t

- 10 CFR 50.:59fqqGRAM .-

., s .

All Design Changes Evaluatec l

l

All Other Changes Screened

- Documentation and Traininc Improved ;

Meets N SAC - 125 Guic e ines

NGAPs 8.10, 8.18 j

e i

i l

AOP J Abodrmal Operating Procedure .. .

+s g Ac":s o Nature l

Tornaco Flooc i

l

Ear:hc ua<e . .

l l

Dam Fai.ure e

l i

AOP.- Abnormal Operating Procedure I

i l Tornado

! l l

1 Secure _oose Eculpmen": '

l Secure Gas Cylincers Cease Cer:ain 03 era: ions

Tornaco Proo" S~:ryc':ure . .

I l

l l

l t

4. ..

I - -

1 l

! . AGP - Abnormal Operating Procedure

)

^

T . _ ,

l L

Ear: 7c ua <e i

l

IV ag ni':ude o" Seismic Even~:

I I

i

! 03 era':ional Basis Ear:hqua<e Design Basis Ear: 1c ua<e l

P an~: Ins 3ec': ion

l

~ .

~

l 'FUTUR LICENSE Rf84EVVAL I

l i

i i'

l l

- No Plans at the l

present time i

l i

f l.

i a .s 1 A-46 RESOLUTION /.

/' !

l '

SOUG l

4 Current Commitments:

l Complete 9R - Spring / Summer 1993 (Under Review l for SSER) l Use A-46 in Entirety w/o Exceptions l Combine with IPEEE to Extent Possible i

Status:

SSEL & Relay Personnel Trained by S' QUG j Preliminary SSEL (Less Relays) Established

& OPS Reviewed; Minimum List Developed to l Facilitate In-House Performance l Tentatively Scheduled Four Personnel for 1992 SQUG Walkdown Training (September & November)

Reviewing Completion Relative to 3 Yr NRC l Allowed Time Frame, Outage Schedule And IPEEE Scope of Work i 1

lPEEEEVENTS .

4 -

_S re_a:p ,*+ vv.~~*'.,

^

c '

-- - L ,'- - ' ' ' 4 - . ~ '.

+

ire EX': erne ='Ood c

Seisrric Eic h Wincs

.: ranS dor:a"lOn

i 6

SEISMIC ' ALUATIONS l

Key Corn aonen~:s ~ rom Ris<

! Assessmen~:

l Fraci ity Cumes i

Convo ute wi~: 1 oct, l Eazard Curves .

EPRl curves as case case

LL\ L curves as sensitivity s~:ucy

_______-___-___--________-____-____________}

s O

WALKDOWN LOG BEAVER VALLEY-UNIT 1 TEAM: A/ } DATE: 6[/~/,!94 Page / of 7 i'

CLDG/ AREA ELEV. LOC. COMPONENT / ITEM ASPECT REVIEWED PHOTO COMMENTS 5%(w May 5 cicle pa_C- S'e m.,s ; G w .ga e C. a t d ,ha ; s o l., + Atte Sbcbc, #"N ' I d n. 4,,,e Flo o< Js;49 ,J.tk u ;e<- dec<,,c!,6 of coe.,3 A-l !;/,d$ pads ~f.g n 0,, 4,p e f Conc <.4 F1de (<oA2 yhoox'~W'<a-i9 otio u x k.s n o' p..p u4tJes a A3 .~tlyft..n co.nc~~inay - s";k,,, i.,..p;7c ,..k,.~~

a

~~p. usa,M wr, c. ,,,.-r. ?; i P.p . ,~~
S!o lo$ * * :n 11 I [
it w <11 A: .s. A c! anat, . } g fL c> ,,
C~, r c .,d: r..., : ox. , m; ri, u t,x. p: ,s y l A-s' *i*.M fb,; '
7oS GAicle 6 a - e yve d d g a lh n A ,,7 Lie c.,,.cim .
s C .,dat Ssr d cn ' art .tu -us9 gun 4, (s, nos " washr;gj.;gu lo.uG= n*t". "A A-6 wJ~ Pu,,p Pu-p 6.,,2. co ma; Ire, : o e ; ,,,,4.a g
" " craek. cn so 1k wall, ~ o.c a
wiefe, 3O5 (\&3 ele A Croelt en ('isor, ~ c. * *
~~wele ~d 'ne s+ n ide of~~
") o s ' ~ 'oee* * '%* rM ^ 3e. o-
.i c-t,w
" * * " '* ;" '" 2 A-7 " hicl'
, Owlsicls, Eg4ede,r Ceectd c- %A c6titisn : C, eel, kt 3 C<a&= c .,
~105 on <3rdiny hjalls vaA,+ l c.~ack1 ~to'la., L., n s.ex* wide A -e ss-4L w.it Costa k - ,
%-, ufr"d Ea%;.c S'u<Cn cs G - A G-dk : Od'.,~;[L L J<i , soulh
.+ r,3 t-al we & & k ior 2GJ '"[* #gt ' of Cecefe Wal{ so ~ * "".< c ,.e W - y ci m ra d A cl
" , ,, a ,,
L. 1<l 3 so 1h *
~161 1. A-1o up r,,- , elavet Adioe ="2(2eA 54*--lse Suda" o 4 G~J CAdiTim : Go& L . .tc i =n+
,1 ~m a.a.s caa,, n ,, p ,, e,,,,,,,n, , c d ENg} o clic( nof corne et au,--
WALKDOWN LOG DEAVER VALLEY-UNIT 1 TEAM: A/M DATE: b!/7.!7I Page d of 7 DLDG/ AREA ELEV. LOC. COMEONENT/ ITEM ASPECT REV.1EWED PHOTO COMMENTS Corda 4mnt Ad'oc~fRA 2.ctar.h C- .is sett csacht c lose.ed.
E,dedor- 26*1' 0 5 '* ""# (go(( Sur$'oce- f.ctca, .soa.%
A - k2
, EGsf DMC ,, c<ock.s up io c . 0 3 *' wids z,,L;,,5 % l4
ib3 W,'oY*"I, aleterved /1-l3 caei ~cl ap u ..z. p .. "
g,u ta- c ~ n.~ w .n a-. w $
S % .ge, % ic ~1 b W Slo <ne ir W;5'I$.'$'.P'.'f"",),':f 'l' '$ , ~
A -ly Lgob.'$1f.'
Mak S W ,6 4 Jur G<-ent L 4<~d.h 1bA' "
p,pe p s r p <ts ll-tr locid.,9 20,]b Correseb,..,Ap su face., f b<oc h 76;2 #
p L ie. f. < r a p p or t . j]-/(,
-unates m.fo s.a. m y o al . " ( ceuesien yt-) es.ppenhakam nuwues e f_,, g g Coofad Saille ~ <-~1 16ker w J 5 S ea,.,a f,*m Ebcevuy Sfrd. 93S' Grock. CP-3 A -IE Co.do.'n u e .cl Ecet Sieleef E .cle < ;se- 9. < Cac.<. Hnhin Looks filee <hhr-3" * [g**2cLm-ks
'
C ce.'en te.. up toj]-79 E.dadoc 235 Eg :p. Haleh of Conc <els Wal{ dup} pot %1 okerveof. i fj[oCmd<l+
, , ,, ,, shake. spa w at E y e A 735' //ofek,lecdiacc.dsf,ucfp< c., /{-20 DU* U~b* E,cfu:er %ve$s Cn Blch Gracle- &j O gagnes MNrl*.3 n x= f
,en.e eks,
=saac esposahy
<. ;4L,k cwe< ,dae A -at zg;,,2 y,gl, Stea,.s Gann-' Concvnte b elosu'G ak Dro;n LL. Grocle, y]e ;l-\tfall Ca, Tak tv-TK ^16 Vlbr' ~Da-age h Co'e.d'- /1- 2 R locich9 A/E'
?la+% m Mjo fTo Co neede. S'u<Dacs yo, had C<aek.s , ~ c . o ; " Gets '
Waucisa u Cr<oc N Eg ;p Halcl1 m%w- 2 3 Lo of<. tug SW tioin , s k:a- G .s. < n t l o y o. 3 h Pa c.,iy; loco fact ekke. space, r y,,,.,,pefy 135' Ga'f he k 'Ta 4 ; a o J A vade s B'd g s h_ ~ R'l _ G A cW"9 0 Phoh ci,d acome out
s ._
=
watxt>OwN LOG sEAvEn VALLEY-UNIT 1 TEAM: A/[A DATE: $!/7!9A Page N of 7 ELEV. LOC. COMPONENT / ITEM ASPECT REV3EWED PHOTO COMMENTS ELDG/ AREA 9thlfier Loww ' C.ee de I-bicais Conc,.1s ad % Mdn losic. Sk<aq<Eic Cede. Pa<T Chtelcl Edavar OIL - De miu<athed Ccsc<de- EJ aw Cewl' Conescle toola OKi Lk s;,cile Ato acces:
"*&*.j?" Grade- s eiscu<<- Shl Pae a- & aclaca-e ; Ceda:wcl A<<~ h>to.k.
Wt" Maeana trknLC, Primar Aux-ilinybkis 7 2 a'- 6" $E"lht l{asonry Woll Leo" **
*"J ?In%l< 'ft C"P(""n')
~~G'** '"3A "P c'"d l3-l Pa<h 0 -'t Starie<mfa nasce< t=res Do.c yy'_ g" 'l A p a. -3 ; crockr I- con << f e- j]- g Cenerstr C roe (<, ~ ao'/~3>~~
~~( - {- B-3 7Kl.'-(! wiUt utsieltkedoro$ ion co dai 6 (2 -~~
P.'c.~f Co res,W o 7 N=/ L/uly h 221 -C Air Cs-f[os- wak Rpincy g,p p ipes G <f t , & ,t u , d ,5,, A+ cce' Support Bas < Pkts Mtisig Gr~t hef~ s~rt"ct~ 23 f'-C' U55 1
% Drbek,,eR n Go,e Lasep'Ai G -T 13evan M (L iL~~ fikt.-~~/h/13aekle') Ta hs not safa6 etaf.d; 7fa'-C ' TisY75 ~lu n3 t? ~ Til.-2.6 af hef(fm o 0%k - occaneA( B-4 '
~~tJ o nom.ny oyty. l *! y p'- f~~
~~4,e. Ars po,.f ceance<ned+ 1cn;.pera occ. )( /3- 7 ,,~~
~~Atse &fe. }Qt rmm+DrJormis% ~ Vi~~
~~6G-Tlf.-1A : miaarl, af # sonic- Q-2~~
') Q' C' Ms'=~ J t= Clutted wah FTp;- . S ' <>iC L& Corrosian o C porsaM. *' - ^)62 &&;h'* . a ~4 5 w e;f'en Floor hE&pprYuP.;>;, iS ') "'"f~C PP I L3 er* ut n,icin w.., u-w s.ee.<r m,- < ,, c.a.La, en cJs Le .<r r.< a 3.a 1.,- pies ; = 9'or.<ea'..r i Frsitf* Ccnceds (^MA- Hs% < Wad C<acks abseaveol " gg,2 '-g ' EI.s.k< i%<-
4-
~~~_.m _ . _ . - .~~
~~. w e~~
9 WALRDOWN LOG l DEAVER VALLEY-UNIT 1 TEAM: M/A DATE: 6[/7[7-7 Page M of_ 7 ELEV. LOC. COMPONENT / ITEM ASPECT REVIEWED PHOTO COMMENTS BLDG / AREA Prl~.,yA vi- SLCRS. Ha.sanry Wo(/ So-il /declife' cal,a,, } o NG **
~~y ,~~
~~'h='y W3 m' aapa nth < ga,closueo ia,y; (a,,4;, , o t,J s,Gry cra,, J H,ssild,'.falaEbo,&&"~~
~~c..ta t c, :~a.' ce,,ct t% dn,k -~~
~~% y Ya.,1< 7se , y 10 & ct o .t<- .~~
~~Faci eli 0 me ( EL Ca <*' ~ " u% W a6o # Mic/4 Bdub 7Se' , PooI a P g, p*fy.j ,f fu,( g,j~~
~~,, , ,, . ..L Pa. I / ca ud Syp. t-Cd% -~~
~~7M-6 IL& &ck s / loolc s o. K .~~
, wutw.tl Lalual S-ere41.< Ga p in Base. Plato l 71r - /,,, s.t Gol P,hirio l o
~~h i l I l~~
~~; 1 l~~
7
~~. _ _ . . _ . . _ . . _ . _ . _ . _ . _ - . _ . _ . _ _ _ _ . _ . _ . _ . _ _ _ _ . . _ _ _ ..- __ _ _ ._ _ _ . ~ . _ _ _ . . _ . _ _ . . _ -~~
l d WALKDOWN LOG, i BEAVER VALLEY-UNIT 1 TEAM: DATE: / Page [ of 7 4 , BLDG / AREA ELEV. LOC. COMPONENT / ITEM ASPECT REVIEWED PilOTO COMMENTS U # Diss si G.., . Ogwra),f $1 D.G. Gs-<< lCondsfiin e P R ato' lang creeks vu- e*3 E-W i etc4g t& Reom Co*"lll D *
~~S' n"*Is> ,; eo-cee. /<. ceif.% ; eda-dmil-f..sug B-ta .~~
! #4 D.G * " i g wn as olowe., else~.1i '.t D G . R.o ,., als. _ " a .2 O.r, . Ritoy /%Irez 4'* < D G- A laIsa.h lo g<.s dves a , c tL Lo,s ofce<w%,pof (?sen F I Oil 77 &.< l? p poke;>>e e<h ='vr=<t; very SI<AlIs . /3-// deawhdcodb., Lfaks 13 * '* *' - P'T toe Ga .,ad caut % o j 3M &a-,s P.ju.am A : S< RW
*[.,*s'i ' R~p BoH C" '* '~
SLc{aae &le d J Ce " *ie- ***'".?.Y.#'*'w'"'estI* coa,s , ; wa ets,"t,'.'.'.uA l ' B -I A m ea.# . l (s a-<, . . a la,, e,). 13 -/ 3 ce-c,.1< woib cl csii P. v plat; g ataty in g coet conetil k [3 -I'l Bed pedue. [ ,, 0,dsala. Lockl*3 ct ' Gu<al Vow Eladim Mark"* i P***t"d'k , , Sadk \ doll of Okis 12,ber in .bedm . .el B-is' '
~~y ,j , & V-eL pa.fi A.k. A .t. 6% g,.,,,,f .5.p,Jak~~
~~,,,a,,J,1, B it " PMa s oye < .~~
(%m ?35 Co,b.I Dik e.c. J<r. a a H.y L&. a ,,fa.;uaJ.in B:%* er:ed i Mea < Co~gJe Hoso-ry Wells / Pres es o f C< acta s;. I fasa-~1 wth - o c c . ;cta,1; h l 6-/7 ",ddj"3[ R**"UF3r5 to-n FAs Gocle.ctllu ,3 &il;,. "kve.l .., sadl.Woll i Savvies' , klatts Fl.. Cal,q* si. c 13 s ' I .G\ elf 'I35 %s'c'E Bsu,lA eie.. k"A 0 -0X- o,C safety.nlicI No< w( S ,iM Ge e<aC Co,cG A - O. k. ; n d .f ... Gsual
'1I 3'-6 Calls' Gays : Fh.,gs,<;,k]dh t~ c 'd*'Alec< crocks. .,, ,,,afi, . saQtj o tso W y l Ceili,,0 Co le<~. Sta.', - possik-l walee okfdklok B 2c *'D,_ $eh- ?,5<l; Ge-sd Co A m o*.
~~A PI,ats cWhat come od 4 . 9~~
~~-wu s . ___-_____.,-_________________...__.__.___.._______._u_...m.~~
_ . __ _ _= _ . . . . _ _ ___ __ _ . _ . _ WALKDOWN LOG ' DEAVER VALLEY-UNIT 1 TEAM: A/[A DATE: (!/ 1 Page b of 7 DLDG/ AREA ELEV. LOC. COMPONENT / ITEM ASPECT REVIEWED PHOTO COMMENTS Se< vic<- Airca,,elita,. Co nt<.I Q. - Air zy,y,gJ;, a y a.pp,, J- Lac e. OUq 7I3'- /> ,, i.,3 R . . ,, G, d. C, c1-e< (J.,:t; 'd ~c2 I lorrasion o&ed$4mkl$edos O~M i e Cahls Tray s Ga., eval Cond;% -Olc ; M -b Henadas Cahls conclui Tiahs,,cesIzn.it cr.cus i pice,. hiade, Line w el S,y of Walc< L filltalab,, Calc <um 13 .2 3 , Me&Q-tw3e CeiI,:,, ALaeo Depcs;t a., Ceil.;,, '.ast.ho,e viaJe ti,,, 13 -;2 <t 2,)',N'lQ 213 ' c' (200M ES*t.
~
~~F/cors ,te$o. s , f,' Ga- ,J c cidrm . ont ou ,:/a~~
" " o,o-ec s.;,tl, gen,< .a,b, je " C d Gnddie 0K na..,.hw?3*'r ~*it Ca61e.VoJt , k/edco(lc E/eci,.6 L R.,e.
~~St<udu. e, 737 VoaLt t<a fiac ti Cs.ka,%ed Gwe<.1 Wela - on C-1~~
- . Haa..,<y Wal!- Crocks oLsewect g,a na C-2 '* "N saw $?
~~c A s, s, ( e's.$ DeliW'b - OIL se.p.x, c w ce a v.,:I- cc,<..in .e u r~ .e~mt;s .~~
~~%g~ct;L ,,,- A<3 ni,s.n .:yp..r. a knes C-3 s,,ie . ,,,, w uw S.a ,dr elaheL,.,~~
~~7ttr ' (~ A Codc.: 4 Co,,eido &Irmi l "Croele" o 6se~<d 1 kra(! ca.,41 tim P<.kalIy n ce <Ia ew Toak C- 4~~
< %<v- kk Pajaa Cupp u t Co<rssim on dict <hy Plaks .. * Li" e C- 6^ ,
WALKDOWN D G DEAVER VALLEY-UNIT 1 TEAM: A/[A DATE: 8 E!74 Page 7 of 7 DLDG/ AREA ELEV. LOC. COMPONENT / ITEM ASPECT REVIEWED PHOTO COMMENTS Safiava , t
~~^' ~ (2Nec Syre<+ Concir-salabJ?) droppo3 he -~~
h ,". & ,i U 72 & $05,~,?~ Ol"e c~ $ 'IP i c la-p ce r r ode A C-6 . LLa. tad LI Lith C.<<asim o h:ewect a, 2 u Fs
;, Geiks atlocleJf.eJnibdaIdptI< C-3 Cenpa n t Rp;,,3 R,,kjaf La<ge. 1 % & iL.1 k. A ccu-d Cesk,L,;,o, v .L Mie Bf .;,ch.h) al.~s cir$had~cermain C-2 C at<. vantf i wcht u.t co, pe.,13elc~ s 4ttaehd +, L.+L Colie ttoJf- mLA m a a!iw '.tor-,' ~; e Shntuai 135 1VS-Ac-s Lin s; = t ', D n. - b/offa Ce,k,ud sagI,.<etJ<d AlatJ k gg,y_ gp aeg, bk. 5pacht W Q Siyl % % Haf f,&,f,,., m k nu 3A% ce,Q,_)- 7,uh%L as Hwl, V cal mi uay nof .Co1 E G % e b ss .n,evids ru.an,w m .imo u,ted u"?,rwe to ~~f Aw R " o Hcd.s a d ]35 e Bladrico{ j%elidia.s Gs J Cowl.h -on. _ " , HCG is tls,f % ,Csila'~ ) , ,, ] S~6 floou E s u,'p d Ha; Cleam Ha3, Qlem 1~solchk 777-[
(2en m W/u s Afo . on!g C- 7 d '
~~" Haafkeel A "~~
C -to l ?CI % M,,'o (?adro; 5 C-H Sdn uoh ., Reeke Se ay 2<dsk is tubs now ] 3%otu ei 243 [Lo (2eem bal[O Cen& o Q peas;W Clof A+ddfaal,4 wcde< ; S,s ,.A C-/1 C-t3 ^!/A e 1o ner belo A fo 0,,/v C-/# tller c,an / / u c-c-~
~~&tcg yanl c<Je 7 paur,a ,st,a,e,,t u y_';,~~
4 - o ATTACHMENT S Outside containment Wall - Concrete Crack Pattern (A-10 & A-12)*
, .p . m ., .. + * ~ ' ,9 ' h ,, e , . ~. . '%e, ~-- A e ?
~~s (. l dk. k 1 7 g.. f h', , ,~~
~~.g ~~~~
~~F g,, ,~~
~~.k? :~~
~~F a _~~
~~. r 4 - . .. ! '. ~.s . D .w r(..A i- . ,v...-,~~
s
,.5,..'. , , y. .?.. !s ?t f_,,] Y ' ' y:;,y ., , ~.g ; 7. . g el . ~!, .s . , . v e ~ .y A ,
~~4 q, .~~
~ = ,. ; ~. - ) _.
~~Designations in parentheses refer to the photograph numbers in the walkdown log (Attachment 4)~~
I I ! Containment-Corrosion of Containment Penetration '
- for Component Cooling Line (C-8) l s / .
I I r-- I I l I .~ l
~~.. (M~ .~~
l .- # 3 P 4
'd .m i * .= *4 $e , . t;iu : -
~~l \~~
~~r. I~~
---..y I 's l ,
~~{ safeguards structure - Water Infiltration and Corrosion of Steel Angles (C-12)~~
~~; F *P 4 I~~
~~i l l l s~~
~~^ .O % Y.~~
~~l- I' , 6' - f:.l7~~
--?o E ' ff -_M< ^.1 ; 1:g. - . . 1,' 7 ?T 1 .. u . g- a ' ~rst..-
~~W} e ~,g ~. :, ma. s . ,.. ... i3 t.?.n.;s.nyM:~~
'~ ,y , ;T *J ,, .s%
~~li . .~~
* .- - ^ * )
[
' "' .j ~5 'E b s *' -?. , . .,, .) '$.t'dU"$1' .4_ .. . a-.%".d;. .e u m .te.?ts $' b $::l t " ' '. 'bflebid.'EI W.'.-M' 2"'
~~i . t i_ . - - - - - - . _ . _ . _ _ . _ _ . _ _ _ _ _ , _ , , _~~
* "s Safeguards Structure-Corrosion of Gliding Support Plates for River Water Piping (C-5) s ^
s
~~'l I~~
~~? 4 5u8 ' 4 T k s Service Building - Water Infiltration and Calcium Formation (d-23) l . . _~2 .~~
.y - ' = . ' u -k , 'W T f '
~~3 e ;;' . . . . 34 sJ $ '. . s .r .~~
~~. f ,'S~~
~~e. ,~~
~ , % .M - 4
~~? ;, - -~~
*g$ ~ .. ,
~~f-. - g e~~
. _ . - - ~ . . . - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
~~l9 .~- Service Building - Control Room Condenser Unit j Degradution of Base /roundation and corrosion of Steel Supports (B-21) l~~
} ' .5 l _
~~i : 4 l~~
~~.. ?~~
t.
~~c. ..li'$ ,; -~~
$ _ g, g '. ' , z et* ,-! e - " ~
~~YEhg,@l /~~
~~, _ g~~
[$= l I l i !- i Metal corrosion of Frame Support (B-22) l i o g , , . .
~
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ML20114D455

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ML20114D455

Text

Dear Mr. Polk:

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Purpose:

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