ML19248D667
| ML19248D667 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/07/1979 |
| From: | Neighbors J Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7908170157 | |
| Download: ML19248D667 (5) | |
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'o UNITED STATES
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NUCLEAR REGULATORY COMMISSION o
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I wAsMNGTON, D. C. 20065
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Docket No. 50-280 JUN 7 TN9 LICENSEE: VIRGINIA ELECTRIC AND POWER COMPANY FACILITY:
SURRY UNIT 1
SUBJECT:
SUMMARY
OF MEETING HELD ON MAY 31, 1979 AT STONE AND WEBSTER (S&W) IN BOSTON MASSACHUSETTS The subject meeting was held with S&W and VEPC0 to review pipe stress analyses and pipe support analyses.
A' list of attendees is attached.
We discussed with VEPC0 items that must be addressed prior to Surry 1 sta rtup.
These items are 1) submittal of final Soil Structure Interaction Report, 2) Interim justification of startup and operation while continuing analyzing, 3) response to IE Bulletin 79-02, 4) response to IE Bulletin 79-06A, 5) emergency bus modifications and 6) inside recirculation pump gh motor bearings.
It is expected that all of these items will be resolved before the saismic review is completed.
Stone and Webster has identified at this time a total of 72 piping analyses and 873 supports analyses to be perfonned. Among them, 29 piping analyses with Engineering Assurance checks have been completed with stresses all within allowables. One hundre< thirty three supports have been analyzed and are conditionally accepteu cending comparison of calculation inputs to as-built MSK.
Stone and Webster expects to complete 47 pipe stress problems (42 original SHOCK-II runs plus 5 runs with Velan value weight variation) and 255 supports all through EA by June 15, 1979.
During the preliminary support evaluation Stone and Webster has identified potential hardware changes on Problems 743, 731A, 731B, and 548A. Analyses for these cases, which may involve using braces for hangers and shims to reduce pipe stresses are still underway.
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3 Meeting Summary for Surry Unit 1 In this meeting, the staff reviewed the results of the following two piping stress analysis packages.
(A) Problem 3228 (Feedwater line - loop B)
(B) Problem 3238 (Feedwater line - loop A)
Preblem 322B used the original ARS whereas Problem 323B used the SSI/ARS with the soil properties corresponding to the lut interaction of SHAKE analyses.
It was found that the analysis procedures are acceptable and stresses within FSAR allowables even if a factor of 1.5 is applied, in
, Problem 3238, to both the inertia seismic stresses and those due to anchor movements.
The staff has also reviewed a total of 42 supports identified in the following lines.
(A) Problem 3238 (Feedwater Line - loop A)
(B) Problem 322A (Main Steam Line - 1 cop B)
(C) Problem 323A (Main Steam Line - loop A)
(D) Problem 5225A-A3 Containment & Recirculation Spray system - R. C.
It was indicated that all the supports reviewed were acceptable even with a factor of 1.5 applied to both inertia seismic stresses and those due to anchor movements.
The question of whether the above fa; tor of 1.5 (to account for the variation of soil properties) should be applied to the pipe stresses and support loads due to anchor movements has been raised in the meeting.
The guidance provided by NRC at this point is as follows:
(A) F or er;ergency loading conditions, the effect of anchor novement need not be considered for the 1.8 Ss check and, therefore, the 1.5 factor need only be t0 be applied to the inertia seismic stress.
Meeting Summary for Surry Unit 1 -
(B) For upset condition, the effect of anchor movement needs to be considered for the 1.2 S check. Therefore, in h
addition to the 1.5 factor which is to be applied to the inertia seismic stress, a suitable factor should also be applied to the stress induced by anchor movements.
Justification of the magnitude of any such factor, pre-sumably less than 1.5, should be provided by the licensee.
Three more safety related pipe lines information was provided to EG&G for EG&G's independent analysis. These lines represent a fraction of the remaining unanalyzed lines under the S&W scope of reanalysis. They are as follows:
(A) Problem 636 (Pressurizer Spray & Relief)
(B)
Problem 562 (Recirculation Spray)
(C) Problem 603 (Component Cooling Water)
O L
Don Neighbo Project Manager Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
List of Attendees cc: w/ Attachment See next page
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LIST OF ATTENDEES AT MAY 31, 1979 MEETING NRC D. Neighbors A. Lee W. Russell R. Maceks (EG&G)
- 8. Saffell (EG&G)
VEPC0 W. Spencer C. M. Robinson R. MacManus G. Strickler S&W B. Crowe S. Rossier K. Reinschmidt E. Homer D. Esielionis R. Hankinson
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1 Meeting Summary for Surry Unit 1 Docket Files NRC POR Local POR ORBI Reading NRR Reading H. Denton E. Case i
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 Mr. Michael W. Maupin Hunton and Williams Post Office Box 1535 Richmond, Virginia 23213 Swem Library College of William and Mary Williamsburg, Virginia 23185' Donald J. Burke U. S. Nuclear Regulatory Commtssion Region II Office of Inspection and Enforcement 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303