ML20063J715

Fourth Set of Interrogatories.Certificate of Svc Encl. Related Correspondence

ML20063J715
Person / Time
Site:	Perry
Issue date:	08/30/1982
From:	Hiatt S OHIO CITIZENS FOR RESPONSIBLE ENERGY
To:	NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD)
References
ISSUANCES-OL, NUDOCS 8209020522
Download: ML20063J715 (5)

Text

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. j r b' RFLATED COHRFSp(Amnarm s August 0ggjTED82 UNITED STATES OF AMERICA NUCLEAR HEGULATORY COMMISSION 6 SEP -1 A10:50 neriCE OF SECRE

- Before the Atomic Safety and Licensing MRr4NG & SERVICE' SRANCH In the Matter of )

)

CLEVELAND ELECThIC ILLUMINATING ) Docket Nos. 50-440 COMPANY, e t al . ) 50-441

) (OL)

(Perry Nuclear Power Plant, )

Units 1 and 2) )

OHIO CITIZENS FOR RESPONSIBLE ENERGY FOURTH SET OF INTERROGATORIES TO NRC STAFF Ohio Citizens for Responsible Energy ("0CRE") hereby propounds its fourth set of interrogatories to the NRC Staff,

• pursuant to the Licensing Board's Memorandum and Order of July 28, 1981 (LBP-81-24, 14 NRC 175).

Issue #5 Statement of

Purpose:

The following interrogatories pertaining to Issue #5 are designed to determine the Staff's assessment ofithe potential at PNPP for the type of accident described in NUREG-0785 and to determine the Staff's regulatory position on this. problem.

4-1. Has the PNPP SDV design met all the criteria and recom-mendations of.IE Bulletins 80-14 and 80-17 (and supplements),

the 8/1/80 letter from Michelson ( AEOD) to H. Denton (NhR),

and Section 4 of the BWH Scram Discharge System Safety Evaluation, dated 12/1/80? Describe in detail any criteria

' ~ not met, and indicate why these deviations are permissible.

8209020522 820B30 PDR ADOCK 05000440

• • DSDU3

o 4-2. In the Staff's opinion, could suppression pool swell hydrodynamic loading on the SDV, SDIV, or HCUs and asso-ciated piping cause pipe breaks or any other damage to these components? Could pool swell disrupt instrumentation in the SDIV or valves in the HCU, thereby impairing the scram function?

4-3. Would water from an SDV pipe break flashing to steam pressurize the containment? Would this condition harm any equipment located in the containment which was not qualified for this condition?

4-4. In the Staff's opinion, does the long common vent line for both banks of the PNPP SDV have the potential for degrading SDV performance, as identified in IE Bulletin 80-17, Suppleme'nt l? -

Issue #9 Statement of

Purpose:

The following interrogatories concerning Issue #9 are designed to ascertain the Staff's regulatory position on radiation dose-rate effects on polymer degradation and to determine the degree to which polymer degradation has been a problem at operating plants.

4-5. When will the final rule on environmental qualification of electrical equipment be published?

4-6. Will PNPP, Units 1 and 2, be required to comply with the l

provisions of 10 CFR 50.49 when it is published? If not, why not? If so, give the time schedule for compliance.

4-7. Explain why the requirement for realistic d'ose-rate testing (for normal operating conditions) was deleted

-3_

s

.n the final version of 10 CFR 50.49(e)(4).

4-8. Will the testing of synergistic effects required by 10 CFR 50.49(e)(7) include the sequential factors identified in NUREG/CR-21567 4-9. Does the Staff intend to promulgate a rule on environmental qualification of mechanical equipment? If so, when?

When would PNPP have to comply with any such rule?

4-10. Produce NUREG-0588, Regulatory Guide 1.89, and any other documents on environmental qualification of equipment pertaining to a radiation environment.

4-11. Produce any and all documents pertaining to the Perry environmental qualification program for electrical and mechanical equipment.

4-12. In the Staff's opinion, could the failures of GE Type l

HFA Relays described in IE Information Notice 82-13 have been caused by radiation-induced embrittlement of l polymers used therein?

4-13. Where were the cables "in service in a nuclear applica-( tion . . . and found to exhibit substantial deterioration" (NUREG/CR-2156 at 8) used? I.e., in a commercial nuclear power plant? Give the name of the facility.

4-14. .ias any polymer degradation been reported in any commercial nuclear power plants? If so, provide all details.

! 4-15. Has further research been conducted on dose-rate and synergistic effects on polymer degradation by Sandia Laboratories (or others)? If so, provide details of the research.

4-16. Identify all documents (NRC and others) in which dose-rate

s and synergistic effects on polymer degradation are described.

4-17. Has research been conducted on dose-rate and synergistic effects on polymers other than those identified in NUREG/CR-2156 and NUREG/CR-2157 (polyethylene, poly-vinyl chloride, polyolefin, ethylene propylene rubber, chlorosulfonated polyethylene, and chloroprene rubber)?

If so, with what results?

Respectfully submitted, Susan L. Hiatt OChE Representative 8275 Munnon Rd.

Mentor, OH 44060 (216) 255-3158

DOCKETED USNRC CERTIFICATE OF SERVICE 12 gg -1 NO S)

This is to certify that copies of the foregoing ,0Hl0 CITIZENS F.4- @O l@puSTAFF SL FOR RESPONSIBLE ENERGY FOURTH SET OF INTERROGATO'upss%$g6E were served by deposit in the U.S. Mail, first c prepaid, this 30th day of August, 1982 to those on thI#AfEEvice list below.

mf Susan L. Hiatt

~

' SERVICE LIST Peter B. Bloch, Chairman Daniel D. Wilt, Esq.

Atomic Safety and Licensing Board P.O. Box 08159 ,

U.S. Nuclear Regulatory Comm'n Cleveland, OH 44108 Washington, D. C. 20555 Dr. Jerry R. Kline Atomic Safety and Licensing Board U.S. Nuclear Regulatory Comm'n Was hington, D.C. 20555 Frederick J. Shon Atomic Safety and Licensing Board U.S. Nuclear Regulatory Comm'n Washington, D. C. 20555 Docketing and Service Section i Office of the Secretary I

U.S. Nuclear Regulatory Comm'n Washington, D. C. 20555 Stephen H. Lewis, Esq.

Office of the Executive Legal Director l

U.S. Nuclear Regulatory Comm'n Washingt.on, D.C. 20555 Jay Silberg, Esq.

1800 M Street, N.W.

"/ashington, D. C. 20036 l

Atomic Safety and Licensing Appeal Board Panel U.S. Nuclear Regulatory Commission Washington, D. C. 20555

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