ML20217D395

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Forwards Request for Addl Info Re Util 990806 Submittal on USI A-46, Implementation Methodology Used at Pilgrim Nuclear Power Station, Per GL 87-02
ML20217D395
Person / Time
Site: Pilgrim
Issue date: 10/13/1999
From: Wang A
NRC (Affiliation Not Assigned)
To: Ted Sullivan
BOSTON EDISON CO.
References
REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR GL-87-02, TAC-M69471, NUDOCS 9910150141
Download: ML20217D395 (5)


Text

I October 13, 1999 h

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Mr. Theodore A. Sullivan Vice President Nuclear and Station Director Entergy Nuclear Generation Company -

- Pilgrim Nuclear Power Station 600 Rocky Hill Road

. Plymouth, MA 02360

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING GENERIC LETTER 87-02 (UNRESOLVED SAFETY ISSUE A-46), " VERIFICATION OF

' SEISMIC ADEQUACY OF MECHANICAL AND ELECTRICAL EQUIPMENT IN OPERATING PLANTS," PILGRIM NUCLEAR POWER STATION (TAC NO.

M69471)

Dear Mr. Sullivan:

. By letter dated August 6,1999, you provided additional information on the unresolved safety issue (USI) A-46 implementation methodology used at the Pilgrim Nuclear Power Station. The NRC has reviewed this information and determined that additional information is needed to complete the review. Enclocad tu the staff's RAl. We request that you respond by October 30, 1999, as discussed with and agreed upon by Stephen Brennion of your staff.

Questions regarding this request should be sent to my attention at the above address or you can contact me at (301) 415-1445.

Sincerely, Original signed by:

Alan B. Wang, Project Manager, Section 2 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-293

Enclosure:

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% [g October 13, 1999 Mr. Theodore A. Sullivan Vice President Nuclear and Station Director Entergy Nuclear Generation Company

Pilgrim Nuclear Power Station 600 Rocky Hill Road

. Plymouth, MA 02360

SUBJECT:

. REQUEST FOR ADDITIONAL INFORMATION (RAl) REGARDING GENERIC LETTER 87-02 (UNRESOLVED SAFETY ISSUE A-46), " VERIFICATION OF SEISMIC ADEQUACY OF MECHANICAL AND ELECTRICAL EQUlPMENT IN OPERATING PLANTS," PILGRIM NUCLEAR POWER STATION (TAC NO.

M69471)

Dear Mr. Sullivan:

By letter dated August 6,1999, you provided additional information on the unresolved safety issue (USI) A-46 implementation methodology used at the Pilgrim Nuclear Power Station. The NRC has reviewed this information and determined that additionalinformation is needed to complete the review. Enclosed is the staff's RAI. We request that you respond by October 30, 1999, as discussed with and agreed upon by Stephen Brennion of your staff.

Questions regarding this request should be sent to my attention at the above address or you can contact me at (301) 415-1445.

Sincerely,

}. A d \LC Alan B. Wang, Project Manager, Section 2 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-293 '

Enclosure:

Pquest for AdditionalInformation -

cc w/ encl: See next page 6 i

v Pilgrim Nuclear Power Station cc:

Resident inspector Mr. C. Stephen Brennion

' U. S. Nuclear Regulatory Commission ' Licensing Superintendent

. Pilgrim Nuclear Power Station Pilgrim Nuclear Pow 9r Station Post Office Box 867 600 Rocky Hill Road Plymouth, MA 02360 Plymouth, MA 023CuS599 Chairman, Board of Selectmen Mr. Jack Alexander 11 Lincoln Street Manager, Reg. Relations and Plymouth, MA 02380 Quality Assurance Pilgrim Nuclear Power Station Chairman, Duxbury Board of Selectmen ' 600 Rocky Hill Road Town Hall Plymouth, MA 02360-5599 878 Tremont Street Duxbury, MA 02332 Mr. David F. Tarantino Nuclear Information Manager Office of the Cornmissioner . Pilgrim Nuclear Power Station Massachusetts Department of 600 Rocky Hi!! Road

__ Environmental Protection Plymouth, MA 02360-5599 One Winter Street Boston, MA 02108 Ms. Jane Perlov Secretary of Pu' " +v Office of the Attorney General Executive Office oi r uolic Safety One Ashburton Place- One Ashburton Place 20th Floor Boston, MA 02108 Boston, MA 02108 Mr. Steve McGrail, Director Dr. Robert M. Hallisey, Director Attn: James Muckerheide-Radiation Control Program . . Massachusetts Emergency Management Commonwealth of Massachusetts Agency Executive Offices of Health and 400 Worcester Road Human Services P.O. Box 1496 174 Portland Street Framingham, MA 01701-0317 Boston, MA 02114 Chairman, Citizens Urging Regional Administrator, Region i Responsible Energy U. S. Nuclear Regulatory Commission P.O. c.Jox 2621 3 475 Allendale Road Duxbury, MA 02331 King of Prussia, PA 19406 o John M. Fulton Assistant General Counsel Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5599 E

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Chairman. Ms. Mary Lampert, Director Nuclear Matters Committee Massachusetts Citizens for Safe Energy Town Hall' 148 Washington Street .

- 11 Lincoln Street Duxbury, MA 02332 Plymcyth, MA 02360

< Mr. William D. Meir,ert -

Nuclear Engineer i Massachusetts Municipal Wholesale

! Electric Company i

P.O. Box 426 "

Ludlow, MA 01056-0426' l I I

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REQUEST FOR ADDITIONAL INFORMATION PILGRIM NUCLEAR POWER STATION. UNIT 1

1. What is the status of allidentified outliers for USl A-46 resolution? For those outliers that have not been implemented please provide a completion schedule.
2. The Generic implementation Procedure, Pevisic.) 2 (GlP-2) provides for several methods of comparing seismic capacity to seismic demand. Method A.1 compares the Seismic Qualification Utility Group Bounding Spectrum to the plant's safe shutdown earthquake (SSE) ground response spectrum. However, GlP-2 places limitations on the use of Method A.1. These limitations are that the SSE ground response spectrum can be used for comparison to the Bounding Spectrum when:
  • The equipment is mounted in the nuclear plant at an elevation below about 40 feet above the effective grade, e The equipment, including its supports, has a fundamental natural frequency greater than about 8 Hz.
  • - The amplification factor between the free field ground response spectrum (GRS) and the in-structure response spectra (IRS) is not more than about 1.5.

In your letter entitled "USl A-46 Supplementary Information," dated August 6,1999, Figures 1,2,3, and 4 contain plots of the IRS and GRS for the Reactor Building at elevation 23 feet, the Turbine Building at elevation 37 feet, the Radwaste Building at elevation 37 feet and the Diesel Generator Building at elevation 34.5 feet. You used GlP 2 Method A.1 to compare the seismic demand to seismic capacity for safe shutdown equipment list items at these locations. However, the amplification factors, above 8 Hz, of these IRS with respect to the GRS appear to be significantly above the 1.5 limit set by GIP-2. Provide a building specific quantitative justification for the use of {'

Method A.1 at the locations where the amplification exceeds the 1.5 limit above 8 Hz.

Enclosure