ML20112E138

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Raises Questions Re Facility,Based on NUREG-0420 & Ser. Topics Include:Rhr,Automatic Switchover of RCIC Sys Suction, Multiplexing Circuitry,Stainless Steel Pipe Cracking & Mark II Load Criteria
ML20112E138
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 05/23/1982
From: Hafner B
AFFILIATION NOT ASSIGNED
To: Joshua Wilson
NRC
Shared Package
ML20105B226 List:
References
FOIA-84-250, RTR-NUREG-0420 NUDOCS 8501150038
Download: ML20112E138 (2)


Text

O Bill Hafner 5h Robinwood Street Mastic, NY 11950 21 July 1982 Robert Gilbert, P.E.

US Nuclear Regulatory Commission Washington, DC 20555 SUBJ: technical inquiry for Shoreham unit 1 RE: my letter of 07 Nhrch 1082 (Bool Dynamic loads / Reactor changes )

my -letter of 08 March 1082 ( Apendix G,10 CFR 50 )

my letter of 10 Fhy 1c82 (MSIV) my _ letter of 23 May 1082 (varicus topics )

RE: our telecon in June on above correspondence

Dear Mr. C11bert,

As we discussed in our last telecen many of the inquiries I had addreened to the NRC were alec a?.drecced to Lilco with the hopec that many would be answered relieving NRC stafr of further paper-work.

Uafortunately, as of this date all such inquiries directed at ccmpany officals have not been answered in any shape, manner, er f e rr..

Regretably, therefore, several of these questions are re-directed at the NRC with an answer requested as soon as possible. However, the large majority of the questions previously asked can be tem-poryily defered which should make the pap (erwork burden somewhat less troublesome. Of the four questions attached ) three are rel-atively direct and should be answerable in a few words or less and only one will probably require a mere lengthy answer.

As stated in previous letters if a telecen reply will be more advantageous to you or the staff please feel free to call during normal business hours :

(516) 261-6046 Thank you, Sincerely,,

{

s EN. (1) as. stated

}

B501150038 840510 PDR FOIA BELAIR84-250 PDR

PAGE T40 Hafner/SNPS ATTACHMENT SUBJ: MSIV leakage for SNPS ni: HURIG-0420, section 6.7, pages 6-53 and 6-54 1/

In the above referenced publication, the applicant (Lilco ) had proposed two changes for technical specs pertaining to the MSIV (1) that the MSIV technical specification leakage rate be increased from 11.5 standard cubic feet per hour (per valve ) to 100 standard cubic feet per hour.

(2 ) that MSIV-leakage rate verification testing frequency be every 18 months during refueling or cold shutdown.

    • What was the apolicants stated reason for requesting such changes ?

2/

What was the original suppression pool volume (at the 5ko M'd level) prior to the decision in 1C68 to increase power to the present 620 M4 level?

3/

4 hat should the pool volume be for a 820K4 Mark II reactor of Ehorehan 8s type ? In other words, if it was going to be redesigned what pool volume would be recc= mended.

4/

Generally what hardware and/or systen mods are necessary to increase the power of a reactor such as was done in the Shoreham esse? Hhve there been any other reactors (ocerating and/or under construction )

which hate under6cr.e s i n i l a r cl.a n g s ?

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