ML20082Q728

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Forwards Info Re Low Frequency Content of Safety Relief Valve Loading,In Response to NRC Request at 830304 Meeting & SER (NUREG-0991)
ML20082Q728
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 10/25/1983
From: Kemper J
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To: Schwencer A
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0991, RTR-NUREG-991 NUDOCS 8312120317
Download: ML20082Q728 (3)


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PHILADELPHIA ELECTRIC COMPANY t

2301 MARKET STREET

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11. fl. I OG!!r:

PHILADELPHIA. PA.19101

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va Docket Nos. 50-352 50-353 Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission i

Subject:

Limerick Generating Station, Units 1 and 2 NRC Environ:nental Qualification Branch (EQB)

Request for Additional Information

References:

1) Meeting, March 4, 1983, NRC EQB et al and PECO Re: Equipment Qualification
2) LGS Safety Evaluation Report (SER) NUREG 0991, August 1983

Enclosure:

Low Frequency Content of SRV Loading Filc:

GOVT 1-1 (NRC)

Dear Mr. Schwencer:

We are pleased to provide, in the Enclosure to this letter, the information requested at the Reference.1) meeting and as discussed in l

the LGS Safety Evaluation Report (Reference 2) page 3-51 regarding low frequency content of SRV loading.

Should any additional information be required, please do not hesitate to contact us.

i Very truly yours,

-4,S4C/-

Enclosure

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Copy to: See Attached Service List.

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8312120317 831025 PDR ADOCK 05000352 E

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5 lu cc: Judge Lawrec.ce Brenner (w/o enclosure)

Judge Peter A. Morris (w/oenclosure)j Judge Richard F. Cole (w/o enclosure),

F Troy B. Connor, Jr., Esq.

(w/o enclosure)'

Ann P. Hodgdon, Esq.

(w/o enclosure)l l

Mr. Frank R. Romano (w/o enclosure) r Mr: Robert L. Anthony (w/o enclosure) f Mr. Marvin I. Lewis (w/o enclosure Judith A. Dorsey, Esq.

(w/o enclosure:

Charles W. Elliott, Esq.

(w/o enclosure?

Jacqueline I. Ruttenberg (w/o enclosurel Zori G. Ferkin, Esq.

(w/oenciesureh Mr. Thomas Gerusky (w/o enclosure)

Director, Pennsylvania Emergency Management Agency (w/o enclosure)

Mr. Steven P. Hershey (w/o enclosure)

Angua Love, Esq.

(w/o enclosure)

Mr. Joseph H. White, III (w/o enclosure)

David Wersan, Esq.

(w/o enclosure)

Robert J. Sugarman, Esq.

(w/o enclosure)

Martha W. Bush, Esq.

(w/o enclosure)

Spence W. Perry, Esq.

(w/o enclosure)

Jay M. Gutierrez, Esq.

(w/o enclosure)

Atomic Safety and Licensing Appeal Board (w/o enclosure)

Atomic Safety and Licensing Board Panel (w/o enclosure)

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Docket and Service Section (w/o enclosure)

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ENCLOSURE o

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La subject:

Low Frequency Content of LGS SRV Loading Discussed at March 4,1983 PECO/NRC Meeting l

Re ferences :

1) LGS Safety Evaluation Report (SER) NUREG 0991, 1

August, 1983

2) LGS Design Assessment Report (DAR)
3) Safety / Relief Valve Quencher Loads: Evaluation of BWR Mark II and III Containments - NUREG-0802 U

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In response to Reference 1, page 3-51, NRC concern expressed "about the applicant's assertion that the Limerick SRV loadings have low frequency content, at around 6 to 10 Hz.", we offer the following:

The Limerick Safety Relief Vsives discharge in the suppression pool through "T"-Quenchers.

The "T"-Quencher design was developed in conj unction with Susquehanna Steam Electric Station (SSES) by Kraf twork U ion (KWU).

n In addition to the design of the "T"-Quencher, KWU also developed the specification for SRV discharge load in the suppression pool.

Discussion p

of LGS SRV Load Definition is found in the Design Assessment Report (Reference 2) Volume 3 Chapter 4, and the discussion of T-Quencher Verification Tests is found in Chapter 8.

In addition, Reference 3 -

NUREG-0802 provides acceptance criteria for hydrodynamic loads on piping, equipment, and structures resulting from SRV actuation.

This NUREG q

recognizes and accepts the low frequency content of "T"-Quencher forcing function which is used in the Limerick design.

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From a review of Power Spectral Density Functions shown in Reference 2 Volume 3 Figures 4.1-28 thru 33, it can be seen that the predominant i

frequency of the SRV forcing function is in the 6 to 10 Hz range.

PSDs from the Karlstein Test shown in Reference 2 Figures 8.5-77-79 confirm l

the low frequency content of the SRV forcing function.

PSDs from the KWU load specification and PSD comparisons from SRV tests in Reference L

l 2, Figures 8.5-80-88 all show the predominant 8 Hertz frequency.

Appendix A of Reference 2 Volume 2 lists and illustrates the g

containment mode shapes 1 thru 23, which cover a frequency range of 3.92 to 39.31 Hz.

Containment response spectra from the KWU generated SRV design load being applied to the Structural Model are shown in Appendix 7

A Figures A.2-1 thru 33.

Several of these indicate " peaks" or significant response in the 6-10 Hz range; e.g., A.2-18,19, 20, 21, 22, 23, 24, 25, 26, 27.

Appendix B of Reference 2 Volume 2 contains the mode shapes, 3

frequencies, and participation factors for the Reactor Building and Control Structure. Response Spectra for the Reactot Building and Control Structure, Figures B. 2-1 thru B.2-58, indicate " peaks" in the 6 to 10 Hz range, most notably Figures B.2-33-43, 47-51.

It is recognized that high frequency content (> 40 Hz) exists as I

shown on various structure floor response spectra in Reference 2 Volume L

2 Appendices A and B.

These response spectra have been included in the l

load combinations used for equipment qualification and for assessing response of equipment due to SRV actuations over the life of the plant.

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