ML19262A489
| ML19262A489 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/22/1972 |
| From: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | John Miller METROPOLITAN EDISON CO. |
| References | |
| NUDOCS 7910300432 | |
| Download: ML19262A489 (3) | |
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Ma rch 22, 19 72 DISTRIBUTION :
AEC PDR PWR Branch Chiefs Local PDR OGC Docke t file CO Docket No. 50-289 DRL Reading Licensing Asst (2)
PWR File H. Schierling S. H. Hanaue r ACRS (16)
F. Schroeder T. R. Wils on Metropoliten Edison Company Attn: Mr. J. G. Miller R. S. Boyd Vice President R. C. DeYoung P. O. Box 542 D. J. Skovholt H. R. Denton Reading, Pennsylvania R. W. Klecker Gentlemen:
E. G. Cas e, DRS In our continuing review of your application to operate the nree Mile Island Nuclear Station, Unit 1, we find that addi-tional information is needed to complete our evaluation.
Se enclosed request pertains to the Babcock & Wilcox topical report
" Qualification Testing of Protection Instrumentation," BAW-10003, dated March 1971. Bis report is part of your Final Safety Analysis Report (FSAR) by reference (FSAR page 7-8).
he addf tional information request corresponds to Section VII of the PSAR and is numbered consecutively to our previous requests.
To maintain our review schedule we will need your complete reply by April 21, 1972. Please inform us within 7 days af ter receipt of this letter as to the date you will be able to submit the requested informatiou to us.
Sincerely,
R. C. DeYoung, Assistant Director for Pressurized Water Reactors Division of Reactor Licensing
Enclosure:
Request for Additional Informati-1486 342 cc:
General Public Utilities Service Corporation, R. W. Heward, Project Manager, 760 Gerry Hill Road, Parsippany, New Jersey 07054 General Public Utilities Service Coraoration, J. R. Worpe, Safety and 1.icensing Manager, 260 Cherry Hill Road, Parsippany, N.J. 07054 Shaw, Pittman, Potts, Trrubridge & Madden, Attn:
Mr. Gerald Charnoff, 910 17th Street, NW, Washington, D. C.
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!)ocket !40. 50-289 Met ropoll tan Edison Company Attn: Mr. J. C. Miller Vice President P. O. liox 542 R eading, Pennsylvania (knt lemen :
In our continuing review of your application to operate the Three Mile Island Nuclear Station, Unit 1, we find that addi-tional information is neuded to complete our evaluation.
The enclosed request pertains to the Babcock & Wilcox topical report
" Qualification Tes ting of Protection Sys tem Ins trumen tation,"
dated March 1971.
This report is part of your Final Safety An alys ia Report (FSAR) by reference (FS AR page 7-8).
The additional information request corresponds to Section VII of the FSAR and is numbered consecutively to our previous requests.
To maintain our review schedule we will need your complete reply by Ap rtl 21, 1972.
Please inform us within 7 days af ter receipt of this letter as to the date you will be able to submit the requested information to us.
Since re ly,
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R. C. DeYoung, As sis tan t Dire ctor for Pressurized Water Reactors Division of Reactor Licensing Enclos ure :
Req ues t for Additional Information cc:
General Public Utilities Service Corporation, R. W. Heward, Project Manager, 260 Cherry Hill Road, Parsippany, New Jersey 07054 General Public Utilities Service Corporation, J. R.
Thorpe,
S'afety and Licensing Manager, 260 Cherry Hill Road, Parsippany, N.J. 07054 Sh aw, Pi t tman, Pot ts, Trowbridge & Madden, At tn:
Mr. Gerald Charnof f, 910 17 th S t ree t, !'W, W as hin g t on, D. C.
20006 1486 343
a RE0l'EST FOR ADDITIONAL INFORMATION METROPOLITA'! EDISON COMPANY THREE MILE ISLA';D GIT 1 (DOCKET NO. 50-289) 7.14 Reference is made in your Final Safety Analysis Report (FS AR) on page 7-8 to the Babcock & Wilcox topical report " Qualification Tes ting of Protection System Ins trumentation," BAN-10003, dated March 1971. With reference to this report provide the following additional information:
a.
The damping f actors. hat resulted from testing of the electronic modules and equipment cabinets ( tables 6-5 and 6-6) appear to be unusually high. Provide a justification for these high damping f actors and in particular for the damping formula on page 6-5.
b.
The coefficient "B," in the formulas on page 6-10, used to compute the percent allowable de error or noise error, is not explained and appears not to be conservative.
Provide the bases for using the coef ficient "B."
c.
Vibration tests were conducted on the electronic modules over a f requency range f rom 7 to 40 Hz.
H owever, their natural frequencies (Table 6-5) lie in a range of 36 to 45 Hz.
To ensure an inactive response to earthquake motion provide a verification that the electronic modules have no natural f requencies below 36 Hz.
d.
The equipment cabine t tests were conducted only along the horizontal axes at f requencies not exceeding 20 Hz, and the response of the electronic modules was not measured.
Provida the bases for using a horizontal test frequency of 20 Hz, for not measuring the module response, and for not conducting vertical vibration tes ts.
e.
Describe the type of supervision provided by Babcock & Wilcox during the remote sensor performance tests that were conducted by the respective equipment manuf acturers (page 1-2).
Verify that vibratory motions were applied to each of the major perpendicular axes independently at f requencies up to 40 Hz.
b