forwards „„.encl., „size:.„.„„„ title: diablo verification,regulatory...

REGULATORY FORMATION'ISTRIBUTION S EM ('RIDS)

AGCESSION NBR:8306170350. DOC ~ DATES 83/06/10 NOTARIZED: NO DOCKETFAGIL:50 275'Diablo Canyon Nuclear Power Planti Unit 1i. Pacific Ga 05000275

AUTH,NAME . AUTHOR AFFILIATIONKRBCHT?NGiJ,E,'S,tone 8 webster 'Engineering 'Corp«RECIP ~ NAME - - RECIPIENT. AFFILIATION

DENTONgH ~ R ~ Office of Nuclear Reactor Regulationg DirectorMARTINJJ ~ B ~ Reg'ion,5I Office of

Director'AhJEATISgG,A, .Paci fic'as E =Electric Co+

SUBJECT: Forwards June 1983,semimonthly open item ~rept;

DISTRIBUTION CODE; D013S COPIES RECEIVED:LTR. „„.ENCL., „SIZE:.„.„„„TITLE: Diablo Canyon (50 275) Independent Design Verification,Program

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t 245 SUMMER STREET. BOSTON. MASSACHUSETTS

ADDRESS Al I CORRESPONDENCE TO P.O. BOX 2325. BOSTON. MASS. 02107

W. U. TELEX: 94 0001SO ETON 94.0977 DESI ON

CONSTRUCTIONREPORTSEXAMINATIONSCONSVI.TINS

END INEERINO

NEW YORKCHERRY HILL. N.J ~

DENVERCHICAGOHOUSTONPORTLAND. OREOONWASHINGTON. D.C.

Mr. G. A. Maneatis, Executive Vice PresidentFacilities DevelopmentPacific Gas and Electric Company77 Beale StreetSan Francisco, CA 94106

June 10, 1983J.'O. No. 14296DCS-464

STONE 8 %REBATER ENGINEERING CORPORATION

Mr. H. R. Denton, DirectorOffice of Nuclear Reactor RegulationU. S. Nuclear Regulatory CommissionWashington, D.C. 20555

J. B. Martin, Regional AdministratorRegion VU. S. Nuclear Regulatory Commission1450 Maria Lane, Suite 210Walnut Creek, CA 94956

Dr. W. E. CooperTeledyne Engineering Services130 Second AvenueWaltham, MA 02254

Docket No. 50-275Diablo Canyon Unit 1

License No. DPR-76

SWEC JUNE SEMIMONTHLY REPORT

Gentlemen:

Enclosed is Open Item Report 8065 issued by SWEC since our last semi»monthly report.

Very ruly ou

. KrechtingProject Engineer, Diablo Canyon Nuclear Power Plant

cc: 4h- Schierling (2)R. R. FrayR. F. ReedyE. T. DenisonM. J. Strumwasser

D. F. FleischakerJ. R. ReynoldsB. NortonA. C. GehrR. B. Hubbard

J. R. PhillipsJ. RoessetM. Axelrad

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OPEN ITEiM REPORT File No. 8o65

File Revision No-l. Date reported to PGEE and TES2. Scheduled for swzc (Originator emimonthly Report No.3. !I i i i iiPP i * i i i: i (if appIicabbeb4. Prepared as a result of:

a. 0 gA Audit and Review Report ofb. g Fie1d Inspection Deficiencyc. 0 Independent Calculation Deficiencyd. 0 Seismic Input Deficiencye. 0 Design Methodology Deficiencyf. Other Deficiency

5. Structure(s), system(s) or component(s) involved:

Please see Attachment 1 through 4

6. Description of Concern:

Please see Attachments 1 through 4

7. Significance of Concern:


8. Recommendation:


% iona tier~:. (Orig irator /Oraanizat ion j

Attachment No, IPatt I of IEOI File 8065

Structure (s), system (s) or component(s) involved:

Feedwater line no. 555

Main Steam Line no. 227

Description of Concern:The horizontal portion of Main Steam Line no. 227 at elevation 179'-

104 is impinged upon by forward get impingement flow from postulated breaknos. 3 and 4 on feedwater line no. 555.

The DCP Jet Impingement Review Sheets do not identify this portion ofthe Main Steam Line as a target for either of these break cases, thoughidentifying the lower horizontal portion of the Main Steam Line as a targetfor reverse flow from break no. 3.

Significance of Concern:

The Main Steam Line is a safety-related target and should be consideredin the safety evaluation regarding the effects of the two postulated FW

break cases.

Recommendation:

The horizontal portion of the Main Steam Line shoulda target for forward flow from postulated break nos.safety evaluation should be performed by the DCP forsafety evaluation should consider the effects on thecoincident with the effects on all other targets forget zones. I

be identified as3 and 4 and aeach break. TheMain Steam Linethe same postulated


Line No. 12 - RCL PP Disc 84 — Break Location No. 2I

Conduit KX-578 (Yellow)Conduit KX-582 (Yellow)

Attachment No.~Page 1 of 2.

EOI Pile 8065

Description of Concern:Conduit KX-582 has been misidentified as conduit KX-578 'onduit KX-578 isidentified as a target on the DCP Jet Impingement Review Sheets for postulatedbreak No. 2 at the Reactor Coolant Pump (RCP) Outlet. The IDVP field inspection,has determined that KX-578 is outside the zone of influence (ZOl) for thisbreak. Conduit KX-582 was determined to be within the Z01 but was not identifiedas a target on the DCP,Jet Impingement Review Sheets

(See Attached Sketch)


The safety evaluation was performed for conduit KX-578 though conduit KX-582 isthe affected target. Conduit KX-582 may contain different cables than conduitKX-578, which may be needed to safely shutdown the plant.

Recommendation:

The DCP should perform a safety evaluation to determine if conduit KX«582 isneeded to safely shutdown the plant for a postulated break at the RCP outlet(Break No. 2 on Line No. 12) ~

Attachment 2Page 2 of 2EOI File 8065

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Attachment Nc.~Page I of 3EOI File 8065


Safety-related (grey) conduit KX-428 (3/4") leading to TE 1315. Letdownline No, 24

'escription of Concern:A pipe rupture on letdown line 24 at break location No. 16 (see Figure 1)results in a blowdown get vertically upward, which impinges upon safety-related (grey) conduit KX-428 (approximately 160" above the break location) ~

(see Figure 2)

Significance of Concern: ~ r

As the conduit is color coded grey and therefore safety-related, it maycontain, cables which are essential for reactor shutdown under conditionsresulting from postulated break 16 on line 24.

Recommendation:

A safety evaluation should be conducted to determine if conduit KX-428is essential for reactor 'shutdown under the conditions associated withthe postulated pipe break 16 on line 24 '

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Attachment No. 4Page 1 of 5EOI File 8065


Vertical supports for line 63, excess letdown line, loop 2 cold leg,.Letdown 3.inc .no. 24.

Description of Concern:

A pipe rupture on letdown line 24 at break location 12 (see Figure 1)results in a traveling get. The traveling )et sweeps horizontally andimpinges upon two of the vertical supports for the excess letdown line63 (see Figures 263) ~


As more than one support for the, safety-related line 63 is being affectedby get impingement from break 12 on line 24, the interaction may affectthe stresses in line 63, such that the piping integrity may be impaired.

Recommendation:

A safety evaluation should be conducted to determine if Excess Letdownline 63 is essential for reactor shutdown under the conditions associatedwith the postulated rupture of Letdown line 24, and to assure compliancewith licensing commitments in FSAR Section 3i6 ~

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