ML20082Q728
| ML20082Q728 | |
| Person / Time | |
|---|---|
| Site: | Limerick |
| 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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i N!WFAR Srr.rjoN P.O. BOX 8699
- 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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