ML20216D884

Forwards Generic Issue Data Sheet Re Possible Generic Problem Re C-E Reactor Coolant Pump Pressure Tap Nozzles Developing Through Wall Cracks Due to Stainless Steel Sensitization

ML20216D884
Person / Time
Site:	Palo Verde
Issue date:	04/06/1983
From:	Crews J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:	Jordan E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
Shared Package
ML20216D344	List: ML20216D339 ML20216D738 ML20216D884 ML20216E083
References
FOIA-87-261 NUDOCS 8706300609
Download: ML20216D884 (3)

Text

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.. So UNITED STATES

< [ 3 ., c NUCLEAR REGULATORY COMMISSION jg c REGION V o . c 1450 MARIA LANE, SUITE 210

,oe WALfJUT ORE S ?' CALIFor.NIA 94596

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April 6,'I983 4 MEMORANDUM FOR: l E. L. Jordan, Director . Division of Engineering j and Quality Assurance, IE

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R. W. Starostecki, Director, Division of Project and Resident Programs, NRC:RI {

i R. C. Lewis, Director, Division of Project and Resident Programs, NRC:RII R. L. Spessard, Director, Division of Project and Resident Programs, NRC:RIII  !

J. E. Gagliardo, Director, Division of Resident, Reactor Project and Engineering Programs, NRC:IV R. L. Bangart Acting Director, Division of Vendor and Technical Programs, NRC:RIV FROM:

J. L. Crews, Director, Division of Resident, Reactor Projects and Engineering Programs, NRC:RV

SUBJECT:

POTENTIAL CENERIC ISSUE: COMUBSTION ENGINEERING REACTOR COOLANT PUMP PRESSURE TAP N0ZZLES DEVELOPED THROUGH WALL CRACKS DUE TO STAINLESS STEEL SENSITISATION FROM FIELD WELD HEAT TREATMENT OF ADJACENT WELDS The enclosed Potentially Generic Issue Data Sheet concerning possible Eeneric problems regarding Combustion Engineering Reactor Coolant Pump  ;

Pressure Tap Nozzles developing through wall cracks due to stainless steel sensitisation from field weld heat treatment of adjacent welds l is forwarded for information and consid a n per TI 2500/3.

.L C ews, Director ivis on of Resident, Reactor Projects and Engineering Programs

Enclosure:

Potentially Generic Issue Data Sheet 83-10

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cc: D. Sternberg, NRC:RV T. Young, Jr. , NRC:RV P. Narbut, NRC:RV C. Heltetnes , AEOD RV Resident Inspectors 09 g70623 .

E.S 7-261 C/,L

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. DATA-SHEET No. 83-10 Appendix A TI 2500/3 4/01/80 POTENIALLY GENERIC ISSUE DATA SHEET 6

• Facility: Palo Verde Docket No(s). 50-528/529/530 Date of Event: July 9, 1982 Inspection (or other Rhport) N/A

1. Brief Description of Issue (Not required if included in supporting data.)

Combustion Engineering Reactor Coolant Pump Pressure Tap Nozzles developed through wall cracks due to stainless steel sensitisation from field weld heat treatment of adjacent welds. This may apply to other pressure nozzles in the hot legs near the Steam Generators.

See attached licensee final report dated March 28, 1983.

2. How Found (If appropriate)

Licensee report.

3. Why Considered Potentially Generic (i.e., reference applicable criteria or give reason).

i System 80 design is not unique to PVNGS.

4. V P.Narbut T. Young,Jr. / D.Sternberg  !

Region Originator Section Chief / Branch Chief 1

5. Other Region reporting that the problem has also been identified by them.

1 Region , Chief Reporting Docket No. )

6. Evaluation by HQ l

I Bulletin / / Circular / / Information Notice / /

Other / /

No other act. ion required / /

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