ML20052D240

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Oh Citizens for Responsible Energy Second Set of Interrogatories Directed to Applicants.Related Correspondence
ML20052D240
Person / Time
Site: Perry  FirstEnergy icon.png
Issue date: 04/29/1982
From: Hiatt S
OHIO CITIZENS FOR RESPONSIBLE ENERGY
To:
CLEVELAND ELECTRIC ILLUMINATING CO.
References
NUDOCS 8205060393
Download: ML20052D240 (3)


Text

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RELaTEu ccaatsawnsncs April 29, 1982 UNITED STATES OF AMERICA C0f yrr.- l NUCLEAR REGULATORY COMMISSION D ~~ ~

Before the Atomic Safety and Licensing Board In the Matter of )

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CLEVELAND ELECTRIC ILLUMINATING COMPANY, Et A1.

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Docket Nos. 50 so ~

50-441

) (Operating License'.)' I ?>

(Perry Nuclear Power Plant, )

Units 1 and 2) )

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T a 2 C~,;g g' 4p+ L, SECOND SET OF INTERROGATORIES g(g7 VTO APP ,/ -

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' Ohio Citizens for Responsible Energy ("0CRE") her % I #

propounds its second set of interrogatories to the Applicants, pursuant to the Licensi'ng Board's Memorandum and Order of-July 28, 1981 (LBP-81-24, 14 NRC 175 (1981)).

Statement of Purpose The following interrogatories are designed to ascertain the susceptibility of the Applicants 5 facility to the LOCA scenario resulting from a pipe break to the scram discharge volume postulated in ICREG-0785.

Interrogatories ~

2-1. }

Produce piping and instrumentation diagrams for the-

!1 scram discharge volume (SDV) and scram discharge instru- a ment volume.(SDIV). Please reference the responses to g .

the subsequent interrogatories to said diagrams when it 2

is appropriate to do so.

2-2.

Produce isometric drawings of the 'SDV and SDIV and all -

associated piping for these.. systems, showing their exact ~

location within the plant, e' specially with regard to the

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, i following:

(a) LPCI pumps (b) LPCS pumps (c) HPCS pumps (d) CRD pumps 2-3. Is any of the equipment listed in (a) to (d) of inter-rogatory 2-2 above located at an elevation below that of j the SDV system or any portion thereof? Provide elevation i I

figures for each item listed in interrogatory 2-2 above 1

and for the SDV system as well. Enumerate any differences f

1 in those figures for Units 1 and 2.

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2-4. ."

Are there valves upstream of all scram discharge piping

..which can be closed in the event of an SDV pipe break? @

If so, enumerate such valves, describing whether they are E E

manually- or power-operated, and if power-operated, :h detailing any interlock systems or circuits which can tl prevent or delay the closure of such valves. 51 2-5. Does Applicants 2 design include redundant and diverse jf indication of an SDV pipe break? I.e., are there tem- Ed gg 55 perature , humidity, or radiation monitors at or near the 53 Ed SDV or SDIV? If so, to what extent? EU 55 2-6. What emergency operating procedures will the reactor h 51 operators have to assure appropriate response to a break 55 4

tZi in the.SDV system? 55

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2-7. Would water from an SDV pipe break in the PNPP design 55

--a flow to or into the suppression pool? Illustrate why this ]h TL would or would not happen. E55 Efi 2-8. Are the water level indicators in the reactor pressure bb!

t" .i2 vessel the only way a break in the SDV would be detected? $$

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If not, please explain. REs P2fd

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2-9. How sensitive to water loss (gpm) is the PNPP reactor pressure vessel?

2-10. Does PNPP follow the GESSAR-238 standard design for the SDV? If not, enumerate and explain any deviations from that standard design.

2-11. Have there been any modifications in the FSAR due to regulatory efforts with regard to SDV pipe breaks?

If so, at what points in the FSAR? Provide any such modifications.

2-12s Is there any way in which an SDV piping break can occur and not be isolated in the current PNPP design? If so, explain.

2-13. What are the dimensions of the largest piping in the

. SDV piping system? Identify that portion of the piping.

2-14. Is operability of the Hi-level scram independent of SDV venting or draining requirements as recommended in the 6/1/80 letter from Michelson (AEOD) to H. Denton (Office of NRR, NRC)?

2-15. Has the SDV system been installed in Unit 1? In Unit 27

. If so, give the date of completion or present percentage of completion for each unit.

2-16. Identify the location in the SDV system of Unit 1 of the damage resulting from the suspected act of vandalism described in PNO-81-109 (December 9, 1981). Describe the measures taken to correct any damage caused thereby.

Respectfully submitted, j usan L. Hiatt OCRE Interim Represnetative 1