ML20237K216

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Advises That Field Review of Seismic Category II nonsafety- Related Installations to Aid in Resolution of IE Insp Item 322/82-30-03 Completed,Per Request.Supports Adequately Installed & Will Perform Intended Function.Summary Encl
ML20237K216
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 06/03/1983
From: Brabazen E
STONE & WEBSTER ENGINEERING CORP.
To: Museler W
LONG ISLAND LIGHTING CO.
Shared Package
ML20237K206 List:
References
FOIA-87-479, FOIA-87-509 NUDOCS 8708270100
Download: ML20237K216 (8)
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[ 31l29 Mr. V. J. Huseler Director, Of fice of Nuclear June 3, 1983 Long Island Lighting Company J.O.No. 11600.02 Shoreham Nuclear Power Station File No. 210-65.1A P.O. Box 618 LIL. 23286 Wading River, NT 11791 I&E INSPECTION ITEM 322/82-30-03 SEISMIC CATEGORY II INSTALLATIONS SHORZllAM NUCLEAR POWER STATION - UNIT 1 WO80-48923 As requested, Stone & Webster Engineering Corporation (SWEC) has completed a field review of Seismic Category II nonsafety-related inota11ations to aid in the resolution of 16E Inspection Item 322/82-30-03. The field review evaluated a total of 125 structural steel and component support installations. The reviev, as conducted, was thorough in each component category. Specifically, each installation was inspected for compliance to f engineering requirements as defined by applicable specifications, drawings, desi 5n criteria, and code requirements.

The field reviau of Seismic Category II component supports has verified

) that all supports were adequately installed and will perform their intended /

f function during all design basis dymanic events. Support deviations, where .

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observed, vere minor and did not compromise the edequacy of the support. t The following provides a summary of the field review and the evaluation results for each component category.

SCOPE OF THE REVILN The scope of the review included the inspection and, evaluation of the belov i

lieted types of couponent supports. This selection was based on LILCO/NRC/SVEC discussions. The actual components in each category are l listed on Attachment A.

Component Category Sample Size I

. c, ca H O yr . _. : -

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1. Cable tray supports 20 Support framea
2. Conduit supports 20 Supports '

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3. Component mounting:
a. Unit coolers 5 Supports CC I'III --
b. Instruments 20 Supports *i(N.> e

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c. Panels 20 Anchorage deta'ils' 8708270100 870824 j co 49_gy,y 7 7/ re,M. J7 ,537 PDR FDIA /

PALASTB7-479 PDR

. - i sto=e v.sosrea s c.,,name coaconario*

June 3 1983

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'1{. I sor:ponent Category k Sample Size '

4. Large bore pipe supports
5. 10 Supports Small bore pipe supports 10 Supports
6. Structural steel 20 Mechers FIELD REVIEW PROCEDURE The field review of each component suppo rt was performed by a team consisting of one SVEC Engineer and one QA/QC Inspector. Each team member was familiar with his respective portions of the engineering documents that controlled the design and installation of each coeponent support prior to the actual field review. These documents typically were as follows:
1. Engineering Design Criteria
2. Applicable Codes & Eagulatory Paquirements
3. Applicable SWEC Standards
4. Design Drawings
5. P4 visions to the issued drawings / specifications; i.e.,  !

E6DCRs/N6Ds '

6. Engineering Specifications
7. Vendor Drawings ne field review was perforned by visually verifying, as a minimum, the following attributes as they applied to each type of cot:ponent support:
1. Geometry of installation
2. Functional characteristics
3. Overall dimensions
4. Verification of member size
5. Weld types, configuration and locations
6. Bolt patterns, sites, and number as specified

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he Engineers and Inspectors involved in these field revieve have extensive knowledge of the requirements for each componeut ca t e go ry, including specific expertise in the related specifications and code requirements.

As each applicable attribute was verified, any deviations between the issued engineering documents and the actual field installation vere documented on,a c'opy of the " Field Review Form" provided in Attachment B.

Any documented deviations were evaluated for their composite ef fect on the l

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.h WJM 3 j supports ability to remain functional during all design basis dynamic .

events. The Engineer made such an. evaluation for each reviewed component and documented the results on the field Review Form. ]

FIELD REVIEW ACCEPTANCE CRITERIA The En ginee r's evaluation of the cotiponent supports ability to remain design basis dynamic events was predicated upon functional during implerantation of the applicable engineering documents. Where the field review verified absolute compliance with the engineering documents, the Engineer designated the component support as acceptable. Where deviations from the engineering documents were identified, the En gineer evaluated '

support acceptability was support acceptability. Where appropriate,The application of engineering l verified by applying engineering judgement.

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judgment was based on the Engineer's knowledge of the following areas:

1. Component support design criteria
2. Specified stress allowables
3. Cods and regulatory requirements
4. Previously specified construction tolerances If these acceptance criteria and judgmental guidelines were not fulfilled, the Engineer deferred making an evaluation until further analysis was performed.

The evaluations were reviewed by the SWEC Lead Structural Engineer for Shoreham.

RESULTS OF THE FIEIS REVIEW The results of the field review for each cociponent category are as follova:

Cable Tray Supports Seismic Category II cable tray supports located within the Reactor Building, Control Building, and Screenwell were reviewed, and all were found to be acceptable. In all cases, the documented deviations were found As a result, the to have little affect on the individual supports. '

Engineer concluded that all reviewed supports would remain functional during all design basis dynamic events. Documented deviations were minor in nature such as an embedded channel nut rotated from the specified position. i Conduit Supports Seismic Category II conduit supporte located within the Reactor Building, Control Building, and Screenwell were reviewed and all were found to be acceptabic. %ere deviations were noted, In all the Engineer evaluated the icpact ca s os , it was concluded that the on the adequacy of the support.

support vould remain functional during all design basis dynamic events.

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required. i Unit Coolers Structural steel unit cooler eupport frames located within the Reactor Building were reviewed. All reviewed support frames were found in compliance with installation details shown on the engineers drawings and were, therefore, acceptable, j

Ins t ruments -

Instrument support details located within the Reactor Building, Control Building, and Screenwell vere reviewed and a u were found to be acceptable.

Final detailed evaluation confirmed l that all supports would remain i functional during all design basis dynamic events.

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Engineering evaluations were performed in instances where observations vers noted during the field review, lhese conditions, subsequently found acceptable by the Engineers, consisted of minor mat e rial substitutions, dimensional differences, and the use alternate hardwa re, including cases where standard fasteners were used without the specified locking devices.

Panels Support and anchorage details for panels located in the Reactor Building and Control Building were reviewed and all were found to be acceptable. In general, documented deviations enhanced the specified support details. For example, one anchor bolt was found not to have been torqued; however, it was located in a group of anchor bolts that were of a larger diameter than caued for on the engineers drawings. Additionally, continuous welds vera provided where intermittent velds were specifind. In a u cases, the Engineer concluded that the reviewed supports would remain functional during all design basis dynamic events. Deviatic x documented in the panel category were minor such as s' continuous weld used where intermittent velding was specified.

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Large Bore Pipe Supports Large bore pipe supports located within the Reactor Building were revio d and all vere found to be acceptable. In au cases, the documented deviations were found to have little affect on the individual supports. As a result, the Engineer concluded that all reviewed supports would remain functional during an design basis dynamic events. Minor deviations were documented such as the substitution of dif ferent membe rs of equivalent or sufficient size.

Small Bore Pipe Supports Small bore pipe supports located in the Reactor and Control Buildings were reviewed and all were found to be acceptable. In all cases, the documented

Ju:.e 3, 1983 s

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i deviations were found to have little effect on the individual supports. As a result, the Engineer concluded that all reviewed supports would remain functional during all design basis dynamic avents. Minor deviations were noted such as veld location differences.

_ Structural Steel ,

Structural steel member installations within the Radwaste Building vere reviewed and all were found to be acceptable. In all cases, any documented deviations were found to have little effect on the individual members. As a result, the Engineer concluded that all reviewed members would remain functional during all design basis dynamic events. Minor deviations were noted such as baseplate bolt locations varying from specified locations.

We trust that the favorable results of this field review will aid you in your e sure of this open item.

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