ML18114A729

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Summary of 790503 Meeting W/Util Re Steam Generator & Reactor Coolant Pump Supports Insps
ML18114A729
Person / Time
Site: Surry  
Issue date: 05/11/1979
From: Snaider R
Office of Nuclear Reactor Regulation
To: Schwencer A
Office of Nuclear Reactor Regulation
References
NUDOCS 7906260107
Download: ML18114A729 (8)
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Text

Docket N

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MAY 1 1 1979 MEMORANDUM FOR:

A. Scllwencer, Chief Operating Reactors Branch #1, DOR fR8M:

Don Neighbors, Project Manager Operating Reactors Branch #1, DOR FROM:

R. P. Sna i der, Task Manager

?eneric Technical Activity A-12

SUBJECT:

SUMMARY

OF MAY 3, 1979 MEETING WITH VEPCO TO DISCUSS STEAM GENERATOR AND REACTOR COOLANT PUMP SUPPORTS INSPECTIONS AT SURRY UNITS NO. l AND 2 On Thursday, May 3, 1979, a meeting was held between representatives of the NRC and VEPCO to discuss the need for inspection of the steam generator and reactor coolant pump supports at Surry Units No. l and 2. A list of att~ndees is attached.

The ma,jor NRG concern is the large amount of.very high strength (250 to

-350 Ksi yield stremgj?tj)=marage steel-inclyded in these structures... This steel is extremely sensitive to.j_n:te~_g_rari~T.~r:*'stte;;s* _CO!"rosio:n~ cr_afkilig_,

even at relatively low stress levels. -Although there are coatings::(s~ch asthe Heresite at_;5urry Units No. land 2) which serve to protect-the steel from exposuri to the environment arid thus exposure to a corrodent,

  • l'l.l,:t~ s1:1bsequent cracking, any coating surface must be confirmed to be 1 ntact. *..

VEPCO agreed to rewrite the support inspection plans to include access'i-ple marage steel. on both the steam generator and reactor coolant pump suppotts.

VEPCO will. also deterriline the stress state {tension or compress.Jon) during 11 norma 1 11 loading for each high strength steel component.

  • t~hen this work h has be~n comp 1 eted, VEPCO wi 11 notify the NRC and a visit to the site wi 11
be arrang-ed,.

,, : *r',~\\<:

The matter of steam generator feed~1ater nozzle replacement was also dis-

. cussed, with VEPCO providing information promised at an earlier meeting.

The feedwater nozzles are unclad carbon steel and contain a carbon steel thermal sl_e~_ve.. No indications of*cracking were found in the blend radius and bore regions of the nozzles, which had been the prime areas of concern for.boiling water re~ctor fe~dwater nozzles which exhibted cracking.

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DAT!!:~-

me FORM 316 (9-76) NRCM 0240

  • u.a. QOVERNME!CNT PRINTING OFFICE: 1178
  • 288
  • 709.

The staff had no further questions on this subject.

Attachment List of Attendees See next page R. Po Snaider, Tas'k'Manager Generic Technical Activity A-12

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DATE~

5/ /79 5/ II /79

  • .-. ~;"-.... ~* * * * * * * *.* * * * * * * * * * ** * * * * * * * * * ** * * * * * * * * * * * * * * * * * * * * *; * * * * * * * * * * ** *

~

u.s *. ooVmRNMEINT PRINTING OP'FICEC: 1978 - zao

  • 769
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  • . r A*,a NRC R. P. Snaider C. D. Sellers.
  • J;: :Zudans*

R. E. Johnson e

List of Attendees John M. Hodge NRC Consultant VEPCO H. S. McKay John T. Benton Stone & Webster Engineering N~ A *. Goldsteiri e

OF'l"IC:l!C~

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Attachment l!lURNAMlt;,o.

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5/ /79 5/ /79, 0 O O O

  • O O O O O O O O O O O O o o o o I o o o
  • O o o o o o o o O o o o O o O o o o o o Io o o o o o o o o o o o o o o O o O O O o o O O
  • O O o' O O O O O O *.* O O O O O O O O O O
  • O O O O O' IO O O O o o o I o O *~ O O O o o o o o o o ~ o: o o o o o o o o o o o o o o o O O O O O O O O O O DATl!C..

MI.C FORM 310 (9-76) NRCM 0240

  • u.s. GOVERNMENT PRINTING OP'FICE: t 971 - 2511 - 769

e Meeting Summary for VEPCO Docket Fi 1 es NRC PDR Local' POR ORBl Reading NRR Reading H. Denton E. Case V. Stello D. Eisenhut B. Grimes R. Vollmer

'A. Schwencer D. Ziemann P. Check G. Lainas D. Davis B. Grimes T. Ippolito R. Reid V. Noonan G. Knighton D. Brinkman Project Manager OELD OI&E { 3)

C. Parrish ACRS (16)

NRC Participants J. Buchanan TERA Licensee Short Service List

  • MAY l 1 1979

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-~ i e

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 MAY 1 1 1979 e

Docket Nos. 50-280 i:H,d '~') ?fl I MEMORANDUM FOR:

A. Schwencer, Chief THRU:

FROM:

SUBJECT:

Operating Reactors Branch #1, DOR

~tlon Neighbors, Project Manager Operating Reactors Branch #1, DOR R. P. Snaider, Task Manager Generic Technical Activity A-12

SUMMARY

OF MAY 3, 1979 MEETING WITH VEPCO TO DISCUSS STEAM GENERATOR AND REACTOR COOLANT PUMP SUPPORTS INSPECTIONS AT SURRY UNITS NO. l AND 2 On Thursday, May 3, 1979, a meeting was held between representatives of the NRC and VEPCO to discuss the need for in~pection of the steam generator and reactor coolant pump supports at Surry Units No. l and 2. A list of attendees is attached.

The major NRC concern is the large amount of very high strength (250 to 350 Ksi yield strength) marage steel included in these struct~res. This steel is extrem~ly sensitive to intergranular.stress corrosion cracking, even at relatively low stress levels. Although there are coatings (such as the Heresite at Surry Units No. land 2) which serve to protect the steel from exposure to the environment and thus exposure to a corrodent, with subsequent cracking, any coating surface must be confirmed to be intact.

VEPCO agr~ed to rewrite the support inspection ~lans to include accessible marage steel on both the steam generator and reactor coolant pump supports.

VEPCO will also determine the stress state (tension or compression) during 11 normal 11 loading for each high.strength steel component.

When this work*

has been completed, VEPCO will notify the NRC and a visit to the site will be arranged.

The matter of steam generator feedwater nozzle replacement was also dis-cussed, with VEPCO providing information promised at an earlier meeting.

The feedwater nozzles are unclad carbon steel and contain a carbon steel thermal sleeve. No indications of cracking were found in the blend radius and bore regions of the nozzles, which had been the prime areas *of concern for boiling water reactor feedwater nozzles which exhibted cracking.*

e MAY 1979 The staff had no further questions on this subject.

Attachment List of Attendees See next page

. P.

aider, Ta,k Manager Generic Technical Activity A-12

e Mr. W. Virginia Electric and Power Company cc:

Mr. Michael W. Maupin Hunton and Williams Post Office Box 1535 Richmond, Virginia 23213 Swem Library College of William and Mary Williamsburg, Virginia 23185 Dona 1 d J. Burke U. S. Nuclear Regulatory Commission Region II Office of Inspection and Enforcement 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 I

I F

L*..

NRC R. P. Snaider C. D. Sellers*

J. Zudans R. E. Johnson e

List of Attendees John M. Hodge NRC Consultant VEPCO H. S. McKay

  • John T. Benton Stone & Webster Engineering.

N. A. Goldstein Attachment

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