ML20052D237

Oh Citizens for Responsible Energy Third Set of Interrogatories Directed to Nrc.Certificate of Svc Encl. Related Correspondence

ML20052D237
Person / Time
Site:	Perry
Issue date:	04/29/1982
From:	Hiatt S OHIO CITIZENS FOR RESPONSIBLE ENERGY
To:	NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD)
References
NUDOCS 8205060390
Download: ML20052D237 (5)

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• k UNITED STATES OF AMERICA iMU7 NUCLEAR REGULATORY C0tGIISSION Before the Atomic Safety and Licensing Board 02 In the Matter of //fy y P3;5g

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) iK CLEVELAND ELECTRIC ILLUMINATING ) Docket Nos. 50-4407 COMPANY, Et t_A1 ) 50-441

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(Perry Nuclear Power Plant, )

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OHIO CITIZENS FOR RESPONSIBLE ENERGL$

THIRD SET OF INTERROGATORIES TO NRC STAFF

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' Ohio Citizens for Responsible Energy ("0CRE e propounds its third set of interrogatories to the NRC Staff, pursuant to the Licensing Board's Memorandum and Order of July 28, 1981 (LBP-81-24, 14 Nhc 175 (1981)).

Statement of Purpose The following interrogatories are designed to determine j

'the Staff's assessment of the potential at PNPP for the type ':

i of accident described in NUREG-0785 resulting from a pipe break 4, 4

to the scram discharge volume and to determine the Staff's  !

regulatory position o'n this problem. h

' ;i Interrogatories g.

3-1.

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Does the so-called " hydraulic" solution or fix to the

~ g BWR ATWS problem involve any modification of the SDV system? If so, describe in detail these modifications 6 '

as they would be required for PNPP. "

3-2.

Does the NRC require temperature, humidity, or radiation  :

i monitors / detectors at or near the SDV to detect breaks in-the SDV or SDIV?

3-3.

Has the Staff-submitted any guidelines or rules requiring. )

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s break detection instruments as described in 3-2 above?

3-4. Has there ever been an SDV pipe break recorded by the

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NRC? If so, give salient details.

3-5. What emergency operating procedures will the NRC require the Applicants to have available in the control room to use in the event of an SDV pipe break?

k 3-6. Does the NRC require training of reactor operators on responding to SDV pipe breaks? If so, describe such training requirements. ,

3-7. Does the Staff currently believe that the isolation of  ;

i the SDV system can be assured in the PNPP design as is?  !

What modifications, if any, would be needed to assure  ;

such isolation?  !

3-8. What arethe Staff's esticates of the maximum flow rate through an SDV pipe break in the Perry design?

3-9. Would water lost through the SDV in 'a break become avail- ,

able for subsequent cooling purposes? If so, indicate the flow path; i.e., from what point to what point would the coolant ultimately pass?  !

3-10. If the response to 3-9 above is in'the affirmative, does the rationale include the possibility of that

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water steaming (flashing) at the break point? {

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3-11. Has the Staff required any modification of the SDV design i

for Applicants' plant? If so, enumerate and explain any such modifications.

3-12. Has the Staff required any changes in the metallurgy of the SDV system for PNPP? If so, describe in detail.

3-13. Will the Applicants be required to perform a fatigue -

analysis on-the Perry SDV system? If so, explain the G

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extent of such requirements.

3-14.

Does the Staff intend to hold the Applicants to GDC 54 i

and 55 of Appendix h to 10 CPR Part 50 with regard to isolation valves within the SDV system? If not, why not?

3-15.

Has the Staff established any surveillance requirements on the SDV system at PNPP? If so, produce those require-ments.

3-16. I Relevant to 3-15 above, will any surveillance include ,

radiography? If so, please elaborate. e r

3-17. r Has the Staff accepted the recommendations of C. Michelson _

L of the NRC AEOD that operability of the hi-level scram E i

be independent of the SDV venting or draining requirements? 5

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(See 8/1/80 letter from Michelson to H. Denton, Office t i

of NMR, NRC.) ~E E

3-18. s Is pipe whip a design consideration for SDV piping =

E design? If so, to what extent? E 3-19. E In the Staff's opinion, did the suspected act of vandalism m E

described in PNO-81-109 cause any irreparable harm to E I_f z

the SDV system that could lead to scram failure or to b=.

a pipe break in the SDV piping? 5 3-20.

In the Staff's opinion, could the deficiency in the hk t ta stress ana,1ysis for the CRD hydraulic system described ==

in the March 11, 1982 letter from D. Davidson of CEI b_

to J. E5 Kepplcr of NRC Region III (water hammer loads from scram valve operation) lead to a . break in the SDV piping? $b EE Are the modifications proposed by the Applicants in said letter sufficient to preclude this't um

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3-21. In the Staff's opinion, could the concerns described in the 3-29-82 letter from A. Schwencer, Division of Licensing, NRC, to D. Davidson, l

A CEI, re " Fast Scram" Hydrodynamic Loads on Control Rod Drive. Systems, lead to a pipe break in the SDV system? -

3 Respectfully submitted, WW s$

Susan L. Hiatt OCHE Interim Representative 8275 Munson Rd.

' Mentor, OH 44060 (216) 255-3158 e

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g eoW CERTIFICATE OF SERVICE ~3 P3:52 6r ;. -

This is to certify that copies of OCRE's SECOND SET; 0F:

INTERh0GATORIES TO NRC STAFF were served TObyAPPLICANTS deposit in the U.S.and Mail,THIRDfirst~ SET OF class, on the postage Service List prepaid, below.this 29th day of April,1982 to those I  !

Susan L. Riatt i SERVICE LIST g

Peter B. Bloch, Chairman 5 Atomic Safety and Licensing Board Daniel D. Wilt, Esq. $

U.S. Nuclear Regulatory Comm'n 7301 Cliippewa Rd.

Washington, D.C. 20555 Brecksville, OH 44141 &j h

Dr. Jerry R. Kline 4 11 Atomic Safety and Licensing Board y U.S. Nuclear Regulatory Comm'n Washington, D. C. 20555 e s,i Frederick J. Shon b Atomic Safety and Licensing Board 55 U.S. Nuclear. Regulatory Comm n e Washington, D.C. 20555 .L g

Docketing and Service Section g 55 Office of the Secretary U.S. Nuclear Regulatory Comm'n . M

g Wkshington, D.C.. 20555 W

James Thessin, Esq. $

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Office of the Executive Legal Director  ;

U.S. Nuclear Regulatory Comm'n g Washington, D.C. 20555 n

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m Jay Silberg, Esq. 555 Ein 1800 M Street, N.W.

washington, D.C. 20036 $

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Atomic Safety and Licensing Appeal Board Panel b 1 U.S. NuclearD.C.

Washington, Regulatory Commission '

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