ML20214K085

Summary of 860923 Meeting W/Util,Pickard,Lowe & Garrick,Inc, BNL & Harmon & Weiss in Bethesda,Md Re Emergency Planning Sensitivity Study.Followup Meeting Scheduled for 861016-17

ML20214K085
Person / Time
Site:	Seabrook
Issue date:	11/21/1986
From:	Long S Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8612020141
Download: ML20214K085 (7)

Text

21 W Y Docket No.: 50-443 APPL.ICANT: Public Service Company of New Hampshire FACILITY: Seabrook Station, Unit 1

SUMMARY

OF MEETING PEl.D ON SEPTEMBER 23, 1986 TO DISCUSS SEABROOK EMERGENCY PLANNING SENSITIVITY STUDY

REFERENCE:

Seabrook Station Risk Management and Emergency Planning Study and Seabrook Station Emergency Planning Sensitivity Study.

Submitted by letter from John DeVicentis to Vincent Noonan, dated July 21, 1986.

A publicly noticed meeting was held on September 23, 1986, at NRC offices in Bethesda, Maryland. The NRC staff was represented by members of the Office of Nuclear Reactor Regulation, the Office of Inspection and Enforcement, and Brookhaven National I.aboratory. The Applicant was represented by members of the Public Service Company of New Hampshire and Pickard,l. owe, and Garrick, Inc.

A list of attendees is included as Enclosure 1.

The purpose of the meeting was to discuss questions raised during the NRC's review of the referenced submitted. The discussion focused primarily on issues related to calculation of containment strength. Other areas of -

discussion included explanation of the accident initiators and release catagories which dominate public risk results. An additional accident sequence involving steam generator tube rupture due to high temperatures created by core melt was also discussed.

A handwritten list of questions was distributed at the meeting. A typewritten and expanded version of this list is included as Enclosure 2. These questions were formally submitted to the applicant by a letter dated October 8, 1986, from Steven M. l.ong to Robert J. Harrison.

A followup meeting was scheduled for October 16-17, 1986, at Brookhaven National I.aboratory, to pursue further details of containment strength calculations.

Steven M. l.ong, Project Manager PWR Project Directorate No. 5 Division of PWR licensing-A N

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.;, - v f3 Meeting Summary Distribution rocket or Central. File NRC Participants NRC POR Steven I.ona 1.ocal PDR Vincent Noonan PD*5 Reading File Warren Lyon J. Partlow l.en Soffer '

V. Noonan Goutam Bacchi Project Manager Donald Perrotti l E. Doolittle Sara M. Davis OGC-Bethesda Richard Barrett E. Jordan Don Hickman l

8. Grimes Charlie Tinkler ACRS (10)

H. Rushbrook cc: Licensee and Plant Service list l

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ATTENDEES Steven I.ong NRC/NRR Project Manager Vincent Noonan NRR/PWR-A, Director John DeVincentis NHY of Director ENG.

David A. Madrand YNSD Asst. Pro.iect Manager Karl N. Fleming Pickard, lowe&Garrick., Inc.

Jim Moody NHY Alfred Torri Pickard, lowed &Garrick., Inc.

Robert E. Sweeney NHY-Bethesda Office Warren I. yon NRC/CPLA/RSB James W. Stacey YAEC/NSO - SB Prof. Eng. Mgr.

Robert E. White NHY - Engineering Bob Youngblood Brookhaven Nati laboratory Charles Hofmayer Brookhaven Natl I.aboratory Goutam Bagchi NRC Len Soffer NRC/DSR0 Kate Silbaugh Farmon & Weiss /NECNP Donald Perrotti NRC/IE/EPB Sarah M. Davis NRC/NRR/DSR0/RRAB Richard J. Barrett NRC/NRR/DSR0/RRAB Don Hickman NRC/NRR/DPLA/F08 Peter I.ittlefield YNSD - Rad. Eng. Mor.

Charlie Tinkler NRC/NRR/DPLA/PSB

o Enclosure 2 4

Comments on Seabrook Overpressurization Calculations Prepared by SMA

1. There is no indication that the c'alculations have been checked or design reviewed.

2. The calculations'are difficult to follow and contain many assumptions. A meeting should be arranged between the originator at these cales and the BNL reviewers to better understand the applicant's position.

3 The basis for the assumptions in the calculations should be fully documented. In particular, the uncertainty factors assigned to various pressure capacities must be explained.

4. Explain the mechanism for transferring the load from the penetration sleeves to the containment wall, in particular, the equipment hatch, when subjected to high strain conditions. The rebars around the penetrations should be assessed to assure that they can resist these loads in addition to the primary pressure induced loads.

S. The calculations use a rebar ultimate strain value of 4.7%, i.e., more than 21 ft. of linear extension for the hoop bars. This linear extension under the high pressure load will be accommodated by formation of cracks in concrete such that summation of all crack widths will approximately be 21 ft. At such a highly cracked conditon, it is questionable whether the pressure will be carried proportionately by the liner plate and the rebars (similar to the elastic conditons) as was assumed in the calculations.

The liner plate over a large crack area may experience a local extension that could lead to failure. Such possibilities cannot be ignored at this high strain value and should be considered in the analysis.

6. It is not clear that the compatibility of strains in the rebars and the liner plate was satisfied in the calculations. For example, the outermost hoop bars will fail before the inside bars and the liner plate reach their respective ultimate strengths. It is not clear that this fact has been reflected in the calculations. In addition, the biaxial stress-strain state of the liner plate should be considered.

7 The combined tension, shear and bending effect at base and spring line levels was not considered in the calculations (Ref. p. 35, assumption 6).

The combined ef fect should be verified.

8. Since 31 cadwelds out of a total of 169 test samples failed at a stress lower than the rebar ultimate strength and there was apparently a construction problem concerning staggering of these welds, provide justification for not using a reduced ultimate strengtly for the rebar.

9. The containment analysis is based on an axisymmetric geometry and loading.

This is not the case due to the presence of adjoining structures such as the fuel building and main steam and feedwater pipe chase. Such non axisymmetric conditions should be identified and their impact on the failure modes and analysis should be assessed.

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10. Only a sample of pipe penetrations are considered in some detail (X-23, X-26 and X-71). The justification to consider only these should be provided.

11. A structural evaluation for electrical penetrations should be provided.

12. The basis for the leakage area assigned to the flued head at failure should be provided.

13. A more detailed evaluation of the impact of punching shear at the Fuel Transfer Building should be provided. The existing evaluation is very approximate.

14. Clarify the extent to which double ended piping failures have been considered in the overall containment'serformance assessment. Provide isometric drawings of all piping attac1ed to containment penetrations.

15. In PLG-0465, page 2-10, Figure 2-3, the conditional frequency of exceeding whole body dose vs distance appears to be driven by the S2 source term. If this is the case, please describe all accident sequences (internal and external events) that contribute to the frequency of the S2 source term given in Table 4-2, pg. 4-7. In particular, define how the timing and size of containment leakage was determined for each of these classes of accident sequences. Justify the appropriateness of the binning of each of the accidents into this particular source term.

16. Provide justification for the liner yield stress increase from the specified yield stress of 32 ksi to a mean yield stress of 45.4 ksi.

17. Indicate the correlation between containment failure sequences and the containment failure modes.

18. Provide the basis for concluding that the sight glasses in the hatches will not fall under high containment temperature and pressure conditions.

19. Document the effect that the recent update in seismic fragilities will have on the conclusions of the PSA results. .

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Fr. Robert J. Harrison Public Service Company of New Hampshire Seabrook Nuclear Power Station cc:

Thomas Dignan, Esq. E. Tupper Kinder Esq.

John A. Ritscher, Esq. G. Dana Bisbee, Esq.

Ropes and Gray Assistant Attorney General 225 Franklin Street Office of Attorney General Boston, Massachusetts 02110 208 State Posue Annex Concord, New Hampshire 03301 Mr. Bruce B. Beckley, Project Manager Public Service Company of New Hampshire Resident Inspector Post Office Box 330 Seabrook Nuclear Power Station-Manchester, New Hampshire 03105 c/o US Nuclear Regulatory Commission Post Office Box 700 Dr. Mauray Tye, President Seabrook, New Hampshire 03874 Sun Valley Association 209 Summer Street Mr. John DeVincentis, Director Haverhill, Massachusetts 01839 Engineering and I.icensing Yankee Atomic Electric Company Robert A. Backus, Esq. 1671 Worchester Road O'Neil, Backus and Spielman Framingham, Massachusetts 01701 116 Lowell Street Manchester, New Hampshire 03105 Mr. A. M. Ebner, Project Manager United Engineers & Constructors William S. Jordan, III 30 South 17th Street Diane Curran Post Office Box 8223 Harmon, Weiss & Jordan Philadelphia, Pennsylvania 19101 20001 S Street, NW Suite 430 Washington, D.C. 20009 Mr. Philip Ahrens,.Esq.

Assistant Attorney General State House, Station #6 Augusta, Maine 04333 Carol S. Sneider Esq.

Office of the Assistant Attorney General Environmental Protection Division Mr. Warren Hall One Ashburton Place Public Service Company of Boston, Massachusetts 02108 New Hampshire Post Office Box 330 D. Pierre G. Cameron, Jr., Esq.

Seabrook, New Fampshire 03874 General Counsel Public Service Company of New Hampshire Seacoast Anti Pollution league Post Office Box 330 Ms. Jane Doughty Manchester, New Hampshire 03105 5 Market Street Portsmouth, New Hampshire 03801 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Mr. Diana P. Randall 631 Park Avenue 70 Collins Street King of Prussia, Pennsylvania 19406 Seabrook, New Hampshire 03874 Richard Hampe Esq.

New Hampshire Civil Defense Agency 107 Pleasant Street Concord, New Hampshire 03301 l

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Public Service Company of Seabrook Nuclear Power Station New Hampshire cc:

Mr. Calvin A. Canney, City Manager Mr. Alfred V. Sargent, City Hall Chairman 126 Daniel Street Board of Selectmen Portsmouth, New Hampshire 03801 Town of Salisbury, MA 01950 Ms. Letty Hett Senator Gordon J. Humphrey Town of Brentwood ATTN: Tom Burack RFD Dalton Road U.S. Senate l Brentwood, New Hampshire 03833 Washington, D.C. 20510 1 1

Ms. Roberta C. Pevear Mr. Owen B. Durgin, Chairman l Town of Hampton Falls, New Hampshire Durham Board of Selectmen Drinkwater Road Town of Durham Hampton Falls, New Hampshire 03844 Durham, New Hampshire 03824

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Ms. Sandra Gavutis Charles Cross, Esq.

Tbwn of Kensington, New Hampshire Shaines, Hardrigan and RDF 1 McEaschern East Kingston, New Hampshire 03827 25 Maplewood Avenue Post Office Box 366 Portsmouth, New Hampshire 03801 Chairman, Board of Selectmen RFD 2 South Hampton, New Hampshire 03827 Mr. Guy Chichester, Chaiman Rye Nuclear Intervention Mr. Angie Machiros, Chairman Committee Board of Selectmen c/o Rye Town Hall for the Town of Newbury 10 Central Road Newbury, Massachusetts 01950 Rye, New Hampshire 03870 Ms. Cashman, Chairman Jane Spector Board of Selectmen Federal Energy Regulatory Town of Amesbury Commission Town Hall 825 North Capital Street, NE Amesbury, Massachusetts 01913 Room 8105 Washington, D. C. 20426 Honorable Peter J. Matthews Mayor, City of Newburyport Mr. R. Sweeney Office of the Mayor New Hampshire Yankee Division City Hall Public Service of New Hampshire l Newburyport, Massachusetts 01950 Company l 7910 Woodmont Avenue Mr. Donald E. Chick, Town Manager Bethesda, Maryland 20814 Town of Exeter l 10 Front Street Mr. William B. Derrickson Exeter, New Hampshire 03823 Senior Vice President Public Service Company of Mr. Richard Strome, Director New Hampshire State Civil Defense Agency Post Office Box 700, Route 1 State Office Park South Seabrook, New Hampshire 03874 107 Pleasant Street Concord, New Hampshire 03301

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