ML17348B273

Forwards Proposed Technical Agenda for Meeting Re Seismic Qualification of Equipment

ML17348B273
Person / Time
Site:	Turkey Point, Saint Lucie
Issue date:	11/22/1991
From:	Rajender Auluck, Norris J Office of Nuclear Reactor Regulation
To:	Goldberg J FLORIDA POWER & LIGHT CO.
References
TAC-M68303, TAC-M68304, TAC-M69483, NUDOCS 9112060250
Download: ML17348B273 (6)

Text

November 22, 1

rg Docket Nos.

50-250,"

50-251 and 50-335 DISTR IBUTION:

OGC NRC Im Local PDRs PDII-2 RDG S.

Varga Mr. J.

H. Goldberg '.

Lainas President -'uclear Division H. Berkow Florida Power and Light Company J. Norris Post Office Box 14000 R. Auluck Juno Beach, Florida'3408-0420 '. Miller M. Sinkule, RII

Dear Mr. Goldberg:

E. Jordan ACRS (10)

SUBJECT:

ST.

LUCIE UNIT 1 AND TURKEY POINT UNITS 3 AND 4 - GENERIC LETTER 87<<02, SEISMIC QUALIFICATION OF EQUIPMENT IN OPERATING PLANTS (TAC NOS.

M69483, M68303, AND M68304) we would like you to address at that meeting.

Please review the enclosure r

promptly and inform either of the undersigned as to when you will be reap to hold such a meeting.

Sincerely, There are a number of issues that need to be resolved concerning the seismic qualification of equipment at St. Lucie, Unit 1 and Turkey Point, Units 3 and 4. Over the past few years, there has been an extensive exchange of information regarding this matter, both in writing as well as by telephone, without closure.

Me would like to meet with you to resolve the remaining outstanding issues.

Enclosed is an agenda listing the technical issues that aJender Auluck, Sr. Project Manager

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St. Lucie Unit 1&2 Turkey Point Units 3&4 CC:

Mr. Jack Shreve, Public Counsel Office of the Public Counsel c/o of The Florida Legislature 111 West Madision Avenue, Room 812 Tallahassee, Florida 32304 Senior Resident Inspector St. Lucie Plant U.S. Nuclear Regulatory Commission 7585 S.

Hwy A1A Jensen Beach, Florida 33457 Mr. Gordon Guthrie, Director Emergency Management Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100 Har old F. Rei s, Esq.

Newman

& Holtzinger 1615 L Street, N.W.

Washington, DC 20036 John T. Butler, Esq.

Steel, Hector and Davis 4000 Southeast Financial Center Miami, Florida 33131-2398 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Mr. James V. Chisholm, County Administrator St. Lucie County 2300 Virginia Avenue, Room 104 Fort Pierce, Florida 34982 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations ABB Combustion Engineering, Inc.

12300 Twinbrook Parkway, Suite 330 Roc kvi 1 le, Maryland 20852 Mr. J.

H. Goldberg Florida Power and Light Company Mr. Jacob Daniel Nash Office of Radiation Control Department of Health and Rehabilitative Services 1317 Winewood Blvd.

Tallahassee, Florida 32399-0700 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 2900 Atlanta, Georgia 30323 Mr. Thomas F. Plunkett, Site Vice President Turkey Point Nuclear Plant P. 0.

Box 029100 Miami, Florida 33102 Joaquin Avino County Manager of Metropolitan Dade County 111 NW 1st Street, 29th Floor Miami, Florida 33128 Senior Resident Inspector Turkey Point Nuclear Generating Station U.S. Nuclear Regulatory Commission Post Office Box 1448 Homestead, Florida 33090 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304 Plant Manager Turkey Point Nuclear Plant Florida Power and Light Company P.O.

Box 029100 Miami, Florida 33102 Mr. R. E. Grazio Director, Nuclear Licensing Florida Power and Light Company P.O.

Box, 14000 Juno Beach, Florida 33408-0420

ENCLOSURE PROPOSED TECHNICAL AGENDA FOR ME"TING The licensee responded to the staff's requests for information by letters dated December 13, 1989 and February 27, 1991.

However, the responses did not sufficiently answer the staff's questions, and consequently, the staff has not been able to proceed with its evaluation of the licensee's program.

In order that the staff can proceed with its review of pre-walkdown requirements, the licensee should respond to the following comments/questions (the item num-bers relate to the staff's August 4, 1989 letter to the licensee):

em 2

The licensee has not adequately discussed the assumptions which it made in developing its program.

For example, the licensee did not discuss whether or not it assumed single active equipment failures as required by GL 87-02.

The licensee has not provided a detailed description of the safe shutdown path.

Therefore, the staff requests that the licensee provides information by categorizing all front line

systems, equipment, instrumentation and

controls, power

sources, support systems and components for each of the following four essential safe shutdown functions during and after a safe shutdown earthquake (SSE):

Reactor reactivity control Reactor coolant pressure control Reactor inventory control Decay heat removal Based on a cursory review of the safe shutdown equipment list (SSEL) provided in the licensee's 2/27/91 submittal, the staff questions the completeness of the SSEL.

For example, the SSEL does not appear to include any valves.

The licensee's response concerning relay evaluation is not acceptable.

The generic program being developed by NUMARC,

EPRI, and the NRC is intended for the Individual Plant. Ex-ternal Event Examination Program (IPEEE), not for USI A-46.

The licensee's program should fully address relay evalu-

ation, and as requested in the 8/4/89 staff letter, the program should list the relay plant identification numbers, the complete manufacturers'odel

numbers, and the floor elevation of each relay on the SSEL; The licensee shall specifically address the acceptance criteria to be used to assure the seismic adequacy of the relays required for safe shutdown.

The licensee needs to address the effect of seismic interactions on relays.

For relays mounted in cabinets, any seismic interaction which results in any equipment physically impacting the cabinet is unacceptable, and must be evaluated as an outlier.

The licensee needs to address potential seismic interactions due to any non-SSEL equipment used for normal plant operations and maintenance activities.

Such equipment may include, but is not limited to, filing cabinets, storage

lockers, gas storage

bottles, refueling equipment, monorails,

hoists, cranes, radiation shields, and any miscellaneous equipment which could potentially cause a seismic interaction with safe shutdown equipment.

~tern 6

The licensee has not fully described the criteria and procedures used for the evaluation of equipment anchorage.

For example, the licensee has not discussed how its program accounts for the effects of bolt edge distance, bolt spacing, and cracked concrete.

The licensee indicated in the 2/27/91 submittal that it used a safety factor of 3.0 for all expansion anchors.

The current staff position is that a safety factor of 3.0 is acceptable for certain equipment items, but some equipment

items, such as cabinets containing relays listed on the SSEL, require a

minimum safety factor of 4.0.

The staff finds that several of the references which the licensee cited for the purpose of anchorage evaluation are out-of-date and may not be acceptable.

In particular, references 1,

3 and 4 listed on page 13 of the 2/27/91 submittal may not be acceptable.

The licensee must describe in detail how the specific information contained in each reference was applied in evaluating equipment anchorage.

In addition to the information described above, the staff requests that the licensee provide detailed information concerning the procedures and criteria used to generate the in-structure response spectra used for equipment evaluations.

This is necessary to resolve recent staff concerns with the in-structure response spectra 'of all plants required to address USI A-46.

After the pre-walkdown requirements have been xeviewed and

approved, the licensee must submit a final report which includes the post-walkdown requirements as specified in items 7 and 8 of the August 4, 1989 letter.