ML18114A447

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Summary of 790326 Meeting W/Util in Surry,Va Re Pipe Stress Problems.W/Status Rept as of 790325
ML18114A447
Person / Time
Site: Surry  
Issue date: 03/29/1979
From: Neighbors D
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 7904190229
Download: ML18114A447 (10)
v • d • e


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MARCH 8 'i} 101@

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Docitet Nos. 50-.280_:)

  • ----------and-50-281 LICENSEE:

Virginia Electric and Power Company (VEPCO)

FACILITY:

Surry~ Units 1 and 2

SUMMARY

OF MEETING HELD mr MARCH 26, 1979 AT SURRY POWER STATION TO

- DISCUSS PIPE STRESS PROBLEMS IN SAFETY RELATED SYSTEMS The subject meeti_ng was held on March 26, 1979, ath the Training Center at the Surry Power Station. The purpo_se of the meeting was to discuss the Surry pipe _stress problems.

The public, including press and TV media~ and Congressman Herb Harris' assistant~ C. Nance, were in attendance in addition to VEPCO and NRC personnel.

A list of V-EPCO and NRC personnel present is attached.

-The status of the VEPCO and Stone and Webster*effort was discussed and i~ included as an attachment. It is VEPCO's plans to verify the as-built pl ant conditions and then rerun all previous SHOCK I anddII calculations (75-100 runs on 15 systems) using the NUPIPE computer code.

For any pipe runs that NUPIPE evaluates to be overstressed, VEPCO

  • currently plans to redetermine new_ floor response spectra based on the soil -structure interaction work submitted and reviewed by the staff in early 1974 in connection with the Surry 3 and 4 construction permits.

They expect the first sets of results from the piping recalculations to be available for NRC review in several weeks at Stone and Wehster facilities in Boston. It will take about one *month before all piping calculations are ready.

NRC stressed the need to ver-ify that all inter-faces are evaluated.

VEP.CO indicated that its *intent J;s to satisf~ctorily develop enough information such tliat interim plant operation would be allowed.

No commitments were maae by NRC other than prompt review of _

docketed submittals and availability t? meet with VEPCO whenever necessary.

VEPCO provided a copy of shutdown procedures and drawings of the ~

affected systems.

After the meeting, a tour of the Unit 1 containment was conducted

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FORM 318 (!ill-76) :NRCM 02"8

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e Meeting Surrmary for Virginia Electric and Power Company for the NRC staff to view~ sampl1ng of lines and hangers:

cc: See next page Attachments:

1. Attendance List
2.

VEPCO/S&W Status

Original Signed By Don Neighbors, Project Mnnager Op~rating Reactors Branch #1 Division of Operating Reactors

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. j Meeting Summary,;or e 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. Ippolito R. Reid.

P. Check G. Lainas 0; Davis B. Grimes V. Noonan

  • F. Shauer R. Bosnak L. Hell er K. Eichman D. Brinkman C. Nelson D. Neighbors P. Polk D. Wigginton OELD J. Scinto J. Souder (LPDR - advance copy)

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

S. Showe, l&E E. Jordon, I&E

. C. Parrish R. Ingram S. Sheppard P. Kreutzer e March 29, 1979 Program Support Branch P-428 Principal Staff Participants R. Fraley, ACRS (16)

Receptionist - for meetings held in Bethesda

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Docket Nos. 50-280 and 50-281 NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 March 29, 1979 LICENSEE:

Virginia Electric and Power Company (VEPCO) i FACILITY:

Surry, Units l and 2

SUMMARY

OF MEETING HELD ON MARCH 26, 1979 AT SURRY POWER STATION TO DISCUSS PIPE STRESS PROBLEMS IN SAFETY RELATED SYSTEMS The ~ubject meeting was held on Marth 26, 1979, at the Trat~in~,

Center at the*Surry Power Station. The purpose of the meeting Was to discus,s the Surry pipe stress problems,

  • The public, including press and TV media, and Congressman Herb Harris' assistant, C. Nance, were in attendance in addition to VEPCO and NRC personnel. A list of VEPCO and NRC personnel present is attached~

The ~tat~s of the VEPCO and Stone and Webster effort was discus~ed and is-included as an attachment... I.tis VEPCO's plans to verify the as-built plant conditions and then.rerun all previous SHOCK I and II calculations*t75..,oo runs on 15 systems) using the NUPIPE computer code.

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For any pipe runs.that NUPIPE evaluates to be overstressed, \\lEP:CO currently plans to redetermine new floor response spectra bas~d on the soi-1-structure interaction work submitted and rev.iewed by the staff in early 1974 in connection with the Surry 3 and 4 construction pennits.

They 'expect the first sets of results from the piping recalcu*lations to be available for NRC review in several weeks at Stone and Webster facilities in Boston. rt will take about one month before all.. piping*

calculations are ready.

NRC stressed t~e need to verify that *;all inter-faces are evaluated.

VEPCO indicated that its intent is to iatisfactorily develo,p enough information such that interim plant operation would be.

a 11 owed.*

  • No *commitments were made by NRC other than prompt review of docketedsubmittals and availability to meet with VEPCO whene\\(er necessary.

VEPCO:provided a copy of shutdown procedures and drawings of the affected systems*.

After.the meeting, a tour of the*u~it l containment was conducted

MeetingSunmary for Virgtnta Electric and Power Company~ 2 ~

March 29, 1979 for the NRC staff to view a sampling of lines and hangers.

cc: See next page Attachments:

1. Attendance List
2.

VEPCO/S&W Status

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Don Ne19 ject Manager Operating Reactors Branch #1 Division of Operating Reactors

NRC D. Nei:ghbors K. DeSai..

P. Riehm D. Burke A. Lee K. Wichman W *. Russel 1 W. Ang, Region II D. Rathbun VEPCO A. Baum C. Stallings B. Sylvia W. Stewart W. Spencer EG&G (NRC Consultant)

R. Macek Stone and Webster T. O'Connor lli9ment 1

e STATUS REPORT AS OF ~RCH 25, 1979 DYNAMIC PIPE STRESS ANALYSIS SURRY POWER STATION -

UNIT NO. l VIRGINIA ELECTRIC AND POW~R CO.MPANY

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INTRODUCTION e

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  • This status report covers the period, from March 13 (date of the NRC Orc.ier-to-Show-Cause letter) to March 25, 1979.

Du.ring this period,* Stone & Webster Engineering Corporation has been analyzing the nuclear safety-related piping systetnti i;-~ferenced in the NRC Order-to-Show-Cause.

Priority for analysis has been given to those particular pip1ng systems which constitute the reactor coolant pressure boundary (Quality Group A) and those systems required to bring the Unit to a safe shutdown and cooldown condition (Quality Group B).

The remaining piping systems affected by the Order will then be analyzed following the analysis of the Unit No. 1 systems; the Unit No. 2 piping systems will be analyzed iri a similar manner.

APPROACH All nuclear safety-related systems identified by the Vepco Nuclear Power Station Quality Assurance Manual as Quality Groups A, B, and C piping systems have been identified. The Quality Group B safe shutdown systems were then identified, as well as the reactor coolant pressure boundary (Quality Group A) piping systems.

From ~hese drawings, those particular piping systems which were originally dynamically analyzed, as defined by the Order-to-Show-Cause, were identified.

There were about fourteen different station systems affected which comprise about 75-100 sepa1-ate analytical computer runs.

Following the identification of the affected piping systems, Vepco determined the priority for analysis to permit interim station operation while the analysis continued through to completion for the balance of ~he affected systems.

All mechanical components (valves, pumps, heat exchangers) are then identified in each affected piping system.

The component drawings, specification, and calculations are retrieved from files and assembled in data packages.

A simi-lar effort is done for the individual pipe support.compo~ents in each affected piping system.

This information will be utilized to review the revised stress loading each mechanical component will see following i:he,dynamic stress analy:-

sis of the associated piping sy~tem.

The affected piping systems will be dynairiically stre~s analyzed using the "NUPIPE" program.

To perform this analysis, the affected piping system geo-metry and piping support type and location must be coded into the program. The piping. geometry and support locatiQn and type. have been field verified and revisions madi to the original ~ipin~ isometric drawings.

All affected piping system drawings, along with the associated supports and*

connecting mechanical - component drawings; wi 11 be reviewed to utilize "as-built" co.nditions as part of this analysis effort.

The "as-built" information is necessary for accurate analytical results, particularly in those cases requiring more detailed analy*sis should significantly increased stresses be determine.d. Th.a "as-built" design effort will commence on or about March 29, 1979.

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The stress analysis will continue during the "as-built" field effort; and as information becomes available, it will be incorporated into the analysis effort, if necessary.

The priorities established for the analysis effort will apply to the "as-built" design effort.

The "as-built" information will be utilized to reconfirm the piping geometry but more importantly will provide information regarding the piping' ha 1nger and support details.. This detailed information will be required to determine the acceptance criteria of each hanger and support in the event that the piping stress loads significantly increase as a result of the analysis.

Upon completion of all analyses, a final report will be issued documenting, as required, the results of _the analysis.

SYSTEMS AFFECTED BY ORDER-TO-S~OW-CAUSE

1.
2.
3.
4.
5.
6.
7.
8.
9.

10 *

11.
12.

Low Head Safety Injection High Head Safety Injections C

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1.

ontainment Rec1rcu at1on Spray

. n Main Steam Auxiliary Steam Generator Feedwater Pressurizer Relief and Spray Piping Residual Heat Removal Service Water Component Cooling Water Containment Vacuum Piping

. 3 In. High Pressurizer Steam I

I Feedwater

13. Fire Protection
14.

Spent Fuel Cooling

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LICENSING REQUIREMENTS

1.

"Final Safety Analysis Report -- Vol. 1-5 (Part B), plus Supplement Vol.

i and 2, and Amendments 14, 15, 17, 19, 20, 21, 22, 23, 24, and 25", Surry Power Station Units 1 and 2, Virginia Electric and Power Company, AEC Docket Nos. 50-280 and 50-281, 1969.

2.

Supplemental material:

(a)

"Surry Nuclear PoweJi Station Preoperational Environmental Radiation Surveillance Program", Report, May 1, 1968 through June 30, 1970, Virginia Electric and Power Company.

  • (b)

"Lateral Load Pile Tests Surry Power Station _....: Virginia Elec-(c)

(d) tric and Power Company", prepared by*Stone & Webster Engineering Corporation, Boston, Massachusetts, July 1968.

"Seismic Desig~ Review,.Equipment and Piping, Surry Power Station",

Virginia Electric and Power Company, Revised September 15, 1971.

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. ;IIQualification Test of Prototype :..._ Vertical Induction Motor --

Containment Recirculation Spray Pump", by J.P. Waggener et al, Frank-lin.Institute Research. Laboratories, Final Report F-C2909, 1971.

"Ade*quacy of the Structural Criteria for the Surry Power Station Units 1 and 2; Virginia Electric and Power Company", AEC Docket Nos. 50-280 and

~0-281, byN.M. Newmark, W.J. Hall, and.A.J. Hendron_, Jr., March 1968.

ANALYSIS The dynamic analysis of the affected_piping systems is divided into two phases:

1.

The piping s.ystems will be analyzed.with the original amplified response spectra to provide a comparison basis against the original code allowables.

2.

Then the same piping systems will be analyzed utilizing a new amplified response spectra which incorporates soil st.ructure interaction.*

In the first case where the original amplified response spectra is used, the "NUPI.PEflprogram will -e_erfonn modal combination using techniques compatible wi.th the original analysis and in: accordance with t_he provisions of the Order to Show Cause; In the second case where the soil structure interaction amplified response spectra i.s used, the "NUPIPE" program will use modal combinations which are compatible with present-day practices.

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