ML19211C063
| ML19211C063 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 12/21/1979 |
| From: | Ellison C, Lanpher L CALIFORNIA, STATE OF |
| To: | NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| References | |
| NUDOCS 8001100031 | |
| Download: ML19211C063 (4) | |
Text
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD
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In the Matter of:
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SACRAMFNTO MUNICIPAL UTILITY DISTRICT
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Docket No. 50-312
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(Rancho Seco Nuclear Generating Station)
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-CALIFORNIA ENERGY COMMISSION'S SECOND SET OF INTERROGATORIES TO THE NUCLEAR REGULATORY COMMISSION Pursuant to the Nuclear Regulatory Commission's rules of practice, particularly 10 C.F.R.
S2.720(h), the California Energy Commisison
(" CEC") hereby files with the Atomic Safety and Licensing Board the following interrogatories to be answered by the NRC Staff.
We request that the presiding officer find that answers to these interrogatories are necessary to a proper decision in this proceeding and that the answers are not reasonably obtain-able from any other source, The definitions included in CEC's First Set of Interrogatories to the NRC, dated November 15, 1979, are incorporated herein by reference.
We request that the NRC Staff answer these interrogatories within 14 days of service hereof, as provided in Section 2.740b.*/
-*/ The CEC understands through a December 20, 1979 telephone conversation with NRC Counsel, that the NRC Staff believes that it has until January 17, 1979, to respond to these interrogatories.
This NRC belief, based upon the parties' 1739 057 8001100 C 3 l
. Interrogatory 1.
Provide NRC's evaluation concerning the acceptability of increased reactor trips and the initiation of auxiliary feedwater in connection with feedwater transients.
Interrogatory 2.
Explain any sensitivities of B & W reactor systems that may require use of HPI in conjunction with feedwater transients.
Interrogatory 3.
B & W reactor systems appear to be unusually sensitive to feedwater transients, particularly because of the once-through steam generator, coupled with the pressurizer sizing, ICS design and PORV/ reactor trip set points.
What design and equipment changes could eliminate this sensitivity?
Are such changes planned?
When?
Interrogatory 4.
What prevented the use of the low pres-sure injection system at TMI?
Interrogatory 5.
At page 6 of SMUD's responses (Set 3) to CEC's First Set of Interrogatories, SMUD states that "[f]or anticipated loss of feedwater transients, void formation does not occur in the B & W Nuclear Steam System."
"Does the NRC Staff agree?
Explain.
Interrogatory 6.
Identify any event involving HPI operation that could result in RCS void formation in B & W reactor systems.
Footnote continued from p. 1
-*/ earlier agreement to extend the discovery schedule, is not shared by the CEC.
A delay in NRC Staff response may force the CEC to request a short extension of discovery so that depositions, now scheduled for January 10 and 11, 1980, will occur after an opportunity to review the NRC's responses.
The CEC urges the NRC Staff, if possible, to respond expeditiously to these interrogatories.
1739 058
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. Interrogatory 7.
In response to CEC Interrogatory #5, the NRC stated that natural circulation can be maintained in lowered-loop plants provided " sufficient inventory exists to raise the liquid level in the steam generators above that of the bottom of the pump discharge nozzle."
Explain the heat removal mecha-nisms required to cool the fuel rod bundles and how heat is removed in the steam generator.
Interrogatory 8.
In response to CEC Interrogatory 15, the NRC Staff states that the " nature" of the oral audits of Rancho Seco licensed personnel is set forth in the Staff's June 27, 1979
" Evaluation of Licensee's Compliance with the NRC Order Dated May 7, 1979." However, in the Evaluation, the audits are merely mentioned but not described in detail.
Please describe each such audit in detail.
Also describe any other audits performed since June 1979.
Interrogatory 9.
What programs or investigations have been conducted by NRC to verify and demonstrate that operational crews have adequate diagnostic capability to identify and resolve multiple failure accident events?
What is the basis for demon-strating acceptable diagnostic skills to the NRC?
What grading standards are used in written and/or oral examinations to assure that operator skills are adequate?
Interrogatory 10.
Describe current NRC programs for maintaining (on a long-term basis) the quality control of written operational procedures (especially for emergency conditions) at 1739 053
. the Rancho Seco facility.
What efforts will be taken on a long-term basis to assure that significant experiences in other nuclear facilities are assimilated by Rancho Seco personnel and incorporated into formally prepared procedures?
Interrogatory 11.
Describe current NRC programs for main-taining efforts to evaluate the quality control of continuing training programs for operators and management personnel at Rancho Seco.
What efforts will be taken on a long-term basis to assure that significant experiences in other nuclear facili-ties are incorporated into the training program at Rancho Seco?
Interrogatory 12.
If the NRC Staff denies in whole or in part any of the requested admissions filed by CEC to NRC Staff, dated December 21, 1979, provide the basis for each such denial.
Respectfully submitted, CALIFORNIA ENERGY COMMISION Christopher Ellison 7.
Lawrence Coe Lanpher Attorneys for the California Energy Commission Date:
December 21, 1979 1739 060
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