ML20147G782
| ML20147G782 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Sequoyah |
| Issue date: | 04/08/1987 |
| From: | King R, Myers H AFFILIATION NOT ASSIGNED |
| To: | James Keppler NRC |
| Shared Package | |
| ML082310263 | List: |
| References | |
| FOIA-87-726 NUDOCS 8801220182 | |
| Download: ML20147G782 (2) | |
Text
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0) i f Ih1 hEg April 8, 1987 To Jim Keppler From Richard King, Henry Myers Re: Sequoyah Questions
\\)um f an 1.
Has the NRC staff prepared a listing of issues specified in NRC ana TVA documents in order that such a list might be compared with TVA's listing of issues which need be addressed prior to and after restart of Sequoyah?
2.
Has the NRC staff evaluated TVA determinations and reviews of existing and missing calculations as described in the nuevuci October 7, 1986 memorandum from J.C. Key to C.A.
- Chandley, the December 17, 1986 memorandum from C.A. Chandley [a the several memoranda titled "Sequoyah Nuclear Plant - (NEB
. ouch ^v Calculation Program - System:
7" What proce have G g.--
been specified for the conduct of such evaluations?
What are dd"sw the results of these ovaluations?
3.
Prior to Sequoyah restart, will the NRC require TVA to have\\
an independent review of calculations in all technical
[7 disciplines similar to the Sargent and Lundy review of I lq te, l p
electrical calculations?
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4.
Will the NRC require that TVA establish an accountable (and traceable) quality electrical load list that will justify fhow ns s equipment, comp 6nent, system 7 and cabic sizing?
How will the NRC obtain and validate assurances from TVA that each electrical circuit and each cable has been verified to be acceptably designed, constructed, and inspected and that sufficient documentation exists to prove that these activities have been done prior to restart?
5.
Prior to Sequoyah restart, does the NRC intend to require TVA to validate that capacity safety margins for diesel generators and battery systems are sufficient to s6ut down the plant EnT tT pr6tect-the public h~ealth anii safety
~~
foflowing design basis events?
6.
Do NRC's acceptance criteria for Sequoyah restart differ from the licensing criteria used in the process leading to the initial Operating License?
If so, what is the nature of any such difference?
Does any such difference constitute a relaxation of safety standards?
What analyses have been done to justify any such changes in criteria and/or relaxat4on of safety standards?
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8801220182 880120 PDR FOIA WANN87-726 PDR.
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Uth s '. t 3 7.
For all the electrical, electrical separation, and fire protection deficiencies identified and reported at Sequoyah, has the NRC reviewed and evaluated each one for acceptable lI4' Y' corrective action?
Has the NRC inspected all those corrective actions that it has approved?
If the NRC has not done so, what is the basis for the decision to not take such actions?
Does the NRC have a plan for addressing specifiedinadequacics in T 8.
t hW+ c l l
especially those concerning TVA's not conducting extensive testing of equipment, components, and materials 9.
Has TVA presented a justification of its method of sampling gh,....,
f' for inspection purposes?
If so, what is the justification?
If not, what is TVA's rationale for not having such a
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justification?
Has the NRC reviewed, validated and approved TVA's sampling methodologies employed in the past?
Why has
{dh
- there been a recurrence of problems where inspections, conducted on small samples of large populations, did not reveal the true extent of deficiencies under investigation?
Do TVA's current sampling methodologies take account of the defects in methodologies used in the past?
- 10. Does the NRC intend to address deficiencies in the following.
areas:
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A. Design criteria that are 1Gss than the industry standard and/or TVA's original criteria?
B. TVA's G-SPECS and their deficiencies in content and application, as well as the deficiencies of other documents that were prepared and implemented, from these specifications?
C.
Lack of acceptance criteria for installation and testing?
- 11. Does the NRC have or plan to develop procedures to assure 1 (), L.
that TVA has a Quality Assurance program that adequately doe \\
implements 10CFR50, Appendix B7 What direction, if any, s
the NRC plan to give TVA in this area?
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