ML18114A623

Summary of 790404 Meeting W/S&W & Util in Boston,Ma Re Sequential Operations of Safety Sys Required to Reach Shutdown in All Conditions & Pipe Sys Stress Reanalysis

ML18114A623
Person / Time
Site:	Surry
Issue date:	04/06/1979
From:	Neighbors D Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 7905300010
Download: ML18114A623 (7)

Text

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6 1919 LICENSEE:

Virginia Electric and-Power Company FACILITIES:

Surry Power Station? Units 1 and 2

SUMMARY

OF MEETING HELD ON APRIL 4, 1979 AT STONE ANO WEBSTER ENGINEERING CORPORATION REGARDING. PIPE STRESS ANALYSES The Surry review team met with tile Virginia' Electric and Pmrer Company

( the license<:) and Stone and Webster at the Stone and,t~ebs ter offices in Boston~ Massachusetts.

A list of attendees is attached.

The first portion of the meeting was spent discussing the NRC Apr.il 2, 1979 1 etter for the licensee I s understanding. The 1 i censee was unable, at that time9 to provide a schedule for responding to the

. NRG 1 etter.

The remainder of the.meeting covered the items listed in attachment

2.

t1e discussed with the 1 i censee the procedures which the licensee proposed to implement during plant shutdown and for mitigating accident

_conditions in the Surry plant when the operating systems are limited to those considered in the priority I category. Since this listing does not include the component cooling water system, neither the RHR system nor the primary coolant pumps could be used during the long term coolings. The licensee presented alternate cooling procedures invo 1 vi ng

• the use of the auxiliary feedivater and safety injection pumps.

The licensee also ou,tlined t~e modified procedures for* operating the plant during accident conditions.

In the ensuing discussion we indicated that the licensee's submittal should provide justification for any interim operations.

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Meeting Summary for VEPCO The licensee had available some preliminary analyses for the feedwater and main steam systems which we were aq)e to review and discuss in relation *to the items in attachment 2.

For these analyses, the stresses were below allowable and the analyses appeared to be satisfactory, contingent upon fie'ld verification of the piping systems.

Attachments:

i. Litt of Attendees

2.

Discussion Items cc: w/attachments See next page Don Neighbors, Pr.oject Manager Operating Reactors Branch #1 Di.vis ion of Operating Reactors l

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Ml.C FORM 318 (9-76) NRCM 02-"l u.11. GOVERNMKNT PR IN.TINO CP'l"IC*: 1970

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e Meeting Summary for Matters Relating to March 13, 1979 Show.Cause Orders Docket Files NRC PDR Local PDR ORB Rdg NRR Rdg C. Kammerer J. Fouchard H. Denton E. Case V. Stello R. Mattson R. Boyd R. DeYoung D. Eisenhut R. Vollmer R. Denise J. P. Knight A. Schwencer D. Ziemann T. I ppo 1 i to R. Reid P. Check G. Lainas D. Davis B. Grimes V. Noonan F. Shauer R. Bosnak L. Heller K. Eichman D. Brinkman C. Nelson D. Neighbors P. Polk D. Wigginton OELD J. Scinto J. Souder (LPDR - advance copy)

I&E ( 3)

M. W. Peranick, I&E OSD ( 3)

S. Showe, I & E E. Jordon, I&E C. Parrish R. Ingram S. Sheppard

• p, Kreutzer "J

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APRIL 6 1979 Program Support Branch P-428 Principal Staff Participants R. Fraley, ACRS (16)

Receptionist - for meetings held in Bethesda

Docket Nos. 50-280 and 50-281 e

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20556 APRIL 6 1979 LICENSEE:

Virginia Electric and Power Company FACILITIES:

Surry Power Station, Units 1 and 2

SUMMARY

OF MEETING HELD ON APRIL 4, 1979 AT STONE AND WEBSTER ENGINEERING CORPORATION REGARDING PIPE STRESS ANALYSES The Surry review team met with the Virginia Electric and Power Company (the licensee) and Stone and Webster ~t the Stone and Webster offices in Boston, Massachusetts.

A list of attendees is attached.

The first portion of the meeting was spent discussing the NRC April 2, 1979 letter for the licensee's understanding.

The licensee was unable, at that time, to provi~e a schedule for responding to the NRC 1 etter.

The remainder of the meeting cover:~Jt'iJ:h~. items listed* i'n* attachment

2.

....., '*' **::*:./*..

We discussed with the lic~nsee the procedures which the licensee proposed to implement during plant shutdown.and for mitigating accident conditions in the Surry plant when the operating systems are limited to those considered in the priority I category. Since this listing does not include the component cooling water system, neither the RHR system nor the primary coolant pumps could be used during the 1 o_ng term coo 1 i ngs.

The licensee presented alternate cool i_ng procedures involving the use of the auxtliary feedwater and safety injection pumps.

The licensee also outlined the modified procedures for operating the plant during accident conditions.

In the ensuing discussi'on we indicated th~t the licensee's submittal should provide justification for any interim opera,tions,

Meeting Summary for VEPCO,, 19; ':

The licensee had available some preliminary analyses for the feedwater and main steam systems which we were able to review and discuss in relation to the items in attachment 2.

For these analyses, the stresses were below allowable and the analyses appeared to be satisfactory, contingent upon field verification of the piping systems.

Attachments:

1. List of Attendees

2.

Discussion Items cc: w/attachments See next page C\\,, /\\~.

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1:J"tV°Y'- l V

Don Ne, ghbc(G, Project Manager Operating Reactors Branch #1 Division of Operating Reactors

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NRC 0:-Nei ghbors W. Russell A. Lee LIST OF ATTENDEES K. Parczewski K. Herring R. Macek (EG&G, NRC Consultant)

VEPCO l~. Spencer C. Robinson M. Kacmarcik G. Strickler L. Johnson Stone and Webster W. Drotleff T. O'Connor R. Klause D. Esiel ionis D. King

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DISCUSSION ITEMS FOR REVIEW OF SAFETY RELATED PIPING SYSTEMS REANALYSIS FOR SURRY UNITS l AND 2 APRIL 4-5, 1979

l. Describe briefly sequential operations of the safety systems required to. reach safe shutdown condition from normal operating and accident condition.

2.

Discussion of pipingi equipment and restraints (~elded support, snubber, anchor... ) modeling techniques for dynamic analysis.

3.

a.

Mathematical models, amplified response spectra, dumping values used in the piping system analysis.

b.

Piping system pressure, temperature, size and material.

4.

Acceptable stress criteria for piping and restraints.

5.

Method of loading combinations for sustained loads, QBE, DBE and differential anchor motions.

6.

a.

Describe the method of combination of the responses due to three component earthquake inpulse using "NUPIPE" pr,:ogram.

b.

11NUPIPE 11 program model combination techniques compatible with the original analysis and present-day practice.

7z Results and evaluation of piping, equipment, nozzles, restraints, and welded attachment including a few fundamental frequencies, forces, moments and stresses.

8.

Comp~rison of original and reanalys_is results~

9.

Results accuracy verification procedur~s.

10.

Identify design and *analysis conservatism.

11.

Piping system restraints modification required based on reanaly~is of piping syste~s.