ML17258A774

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Forwards Responses to SEP Topics III-6 Re Seismic Design Considerations & III-11 Re Component Integrity.Detailed Schedule for Future Analyses Required for Completion of Open Items Will Be Provided as Soon as Possible
ML17258A774
Person / Time
Site: Ginna Constellation icon.png
Issue date: 02/06/1981
From: White L
ROCHESTER GAS & ELECTRIC CORP.
To: Crutchfield D
Office of Nuclear Reactor Regulation
References
TASK-03-06, TASK-03-11, TASK-3-6, TASK-RR NUDOCS 8102100511
Download: ML17258A774 (8)


Text

REGULATORY IFORMATION DISTRIBUTION S EM (RIDS)

ACCESSION NBR:8102100511 DOC,DATE: 81/0P/06 NOTARIZED:

NO DOCKET FACIL':50 244 Robert Emmet Ginna Nuc'lear Planti Unit ii Rochester G

05000244 AUTH>,NAME AUTHOR AFFILIATION H'HI T E "P L s D s Rochester Gas 8 Electr ic Carp.

RECIP ~ NAME RECIPIENT AFFILIATION CRUTCHF IELDi D ~

Operating, Reactors Branch 5

SUBJECT:

Forwards responses to SEP Topics III-6 re seismic design consider ations 8 III-lire component integr ity,Detailed schedule-for" future analyses required for comple,tion-open items will be provided as soon as possible.

DISTRIBUTION CODE:

AOZSS COPIES RECEIVED:LTR J." ENCL SIZE:-

J'ITLE:

Seismic Review for SEP Plants, NOTES: 1 copy!SEP Sects Ldr.

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Attachment Open Issues, R.E. Ginna Seismic Review 1,2.

3.

Auxiliary Building and Turbine Building Bracing.

Rochester Gas and Electric is in the process of develop-ing a Structural Review Evaluation in response to the concerns expressed in this report.

Because of the short time between receipt of NUREG/CR-1821 (January 15, 1981) and the required response date (February 6,

1981),

a detailed schedule is not yet available.

The schedule for evaluation of this bracing will be provided by March 23, 1981.

Essential Service Water Pumps.

As noted in the recom-mendation, RG&E is evaluating the feasibility of making the modifications required to provide additional seismic margin for the Service Water Pumps, above that provided for in the original design methodology.

Concurrently, RG&E is studying the requirements for a "dedicated shutdown system",

which could include a provision for Service Water.

The RG&E response concerning the dedicated shutdown system will be submitted by March 19, 1981.

It is important to note that no immediate steps to correct the Service Water System are warranted.

A means of safe shutdown without Service Water has been reviewed by the NRC staff and deemed acceptable as an interim means.

This shutdown method was described in RG&E's "Fire Protection-Shutdown Analysis" dated December 28, 1979.

It was noted as an acceptable interim measure in the staff's "SEP Review of Pipe Break Outside Containment.,

Topic III-5.B", transmitted by letter of June 14, 1980 from Dennis M. Crutchfield to Leon D. White, Jr.

4,5.

Component Cooling Surge Tank and RWST.

The design of measures to increase the seismic margins above those provided by the original design methodology is presently under study.

Because of the short time available between receipt, of NUREG/CR-1821 (January 15, 1981) and the required response date (February 6,

1981) a detailed schedule for analysis and modification has not yet. been generated.

A schedule for performing this evaluation will be provided by March 23, 1981. It is expected that the results of the evaluation can be made available on or about June 30, 1981.

6.

Motor-Operated Valves.

As recommended in NUREG/CR-1821, the Ginna Piping Seismic Upgrade Program will account for the stresses induced by valve eccentricity into the piping analysis.

The analysis will be performed in

accordance with the "Design Criteria, Ginna Station, Seismic Upgrade Program",

Revision 1, dated September 1,

1980.

Steam Generator, Reactor Coolant Pump, Pressurizer, and Control Rod Drive Mechanism.

The following stress reports are included for review:

a)

Vertical Steam Generator Stress Report", Wedler, R.P., April 1969, Westinghouse, Tampa.

b)

"44 Series Steam Generator External Load Analysis Update",

Nagayasu, K., De Rosa, P. P.,

May 1975, Westinghouse, Tampa.

c)

"L-106 High Speed Control Rod Drive Mechanism Stress Analysis", Ganguly, S.K.,

June

1968, Westinghouse, Cheswick.

d)

"RGE Seismic Frame Calculations",

Howell, R.,

Westinghouse Commercial Atomic Power Division, Monroeville.

e)

"Seismic Analysis of Shaft Seal Reactor Coolant Pump", van Allen, F.K., July 1968, Westinghouse, Cheswick.

f)

"Pressurizer Design Report," Mendolia, F.J.

and

DeRosa, P.P.,

September

1969, Westinghouse, Tampa.

Battery Racks.

The modification to replace the wooden battery racks are scheduled to be compl'eted during the Spring 1981 refueling outage.

Motor Control Centers and Switchgear.

These items are being evaluated in conjunction with the "Seismic Operability" program being performed as an SEP Owners Group project.

The Owners Group has hired Westinghouse to lead this program.

A meeting to present the proposed program is presently scheduled for March 5, 1981.

'Control Room Electrical Panels.

Proper anchor bolt design and placement, was verified in conjunction with the "Anchorage'and Support of Safety-Related Electrical Equipment" program, first described to the NRC in a letter from RGGE dated February 11, 1980.

The status of this program was transmitted to the NRC by letter of December 22, 1980.

The evaluation of internally-mounted equipment, is being performed in the "Seismic Operability" program, noted in 12, 13, above.

Electrical Cable Raceways.

The seismic qualification program for cable trays is being performed as~ an SEP Owners Group project.

This program was discussed in a letter from Richard E. Schaffstall (KMC) to

SI I'

IA

3 Dennis M. Crutchfield (NRC) in a letter dated August 28, 1980.

Since that time, the SEP Owners Group has hired URS/Blume to lead this program.

URS/Blume made a presentation to the NRC staff concerning this program on October 3, 1980.

A meeting to update the staff on the progress of the program is presently scheduled for March 5, 1981.