ML20238C224
| ML20238C224 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Sequoyah |
| Issue date: | 07/21/1987 |
| From: | Myers H HOUSE OF REP. |
| To: | Harold Denton NRC |
| Shared Package | |
| ML082310219 | List: |
| References | |
| FOIA-87-726 NUDOCS 8712300136 | |
| Download: ML20238C224 (4) | |
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C ~.l July 21, 1981 To Harold Denton From Henry Myersg4 RE: NRC ACTIONS CONCERNING RESTART OF SEQUOyAH The following questions pertaining to the NRC's rme.eu of Sequoyah have emerged from our inquiry into NRC's regulation of TVA's nuclear program.
1.
On March 28, 1987 Mr. Dallas Hicks sent to Chairnan Udall and Dingell a letter enumerating 28 items pertaining to Sequoyah.
On April 9, the Chairmen transmitted Mr. Hicks' letter to the Commission requesting the Commission's position with respect to; the items in Mr. Hicks' letter.
To which of the 23 items enumerated in Mr. Hicks' March 28 letter to Chairmen Udall and Dingell will there be a substantive response prior to Sequoysh restart?
3 2.
Which of the issues enumerated in Commissioner Asselstine's March 18, 1987 memo to Mr. Stello does the NRC staff consider adequately addressed by TVA in its June 10, 1987 response to the NRC?
With respect to each such issue, what is the nature of analysis, inspection, and/or hardware modification that will be required prior to restart of Sequoych 2?
3.
TVA has underway an upgrading of design criteria, standards, specifications, G-Specs, procedures, and other documents that govern plant operations, maintenance and modification.
Certain plant modifications will result from this upgrading of such criteria, etc.
To what' extent does the NRC intend to develop a comprehensive check list of items required for completion prior to restart?
4.
Following the " vertical slice" independent review of the Sequoyah ERCW System, what criteria will the NEC use, in determining which problems, identified as a result bf this j
review, shall be corrected prior to Sequoyah restart?
What l
criteria will the NRC apply in determining whether daa results of the ERCW review indicats the necessity of additional reviews prior to Sequoyah restart?
l 5.
Which of the itoms designated by TVA as Conditions Adverse t6 Quality (CAQs) will' be required to be resolved through inspections and/or harddare modifications prior to restart of Sequoyah?
6.
Has NRC evaluated the' adequacy of TVA's program for
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addressing employee concerns?
What is ths. result of that evaluation?
What criteria will the NRC apply in determining whether, prior to Sequoyah restart, TVA will be required to resolve specific employee concerns?
WANN87-726 PDR r
i 7.
Prior to Sequoyah restart, what will the NRC require with respect to a determination of the applicability to Sequoyah of deficiencies identified at Watts Bar through the Black & Veatch review, MSRS reviews, INPO and NRC inspections, and the employee ioncerns program?
What criteria will the NRC apply in determining whether items, identified at Watts Bar and having 7eneric applicabilities at Sequoyah, will need to be resolved pricr to Sequoyah restart :through design modifications, inspections, j
and/or hardwar e modif' cations?
8.
Prior to_Sequoyah restart, will the NRC require that TVA certify that Gequoyah conplies with' licensing commitments and all applicable Ccncission requirements 7 9.
Given the-history of TVA failing to comply with the requirements of 10CFR50, what actions will the NRC take prior tc sequoyah restart in order to determine that adherence to. Appendix 3 has been achieved at Soquoyah and within other TVA l
organizations upon which the safe operation of Sequoyah depends?
10.
What will the NRC require with respect to recalculations and/or review of calculations for safety-related items, associated Class IE items, and norsafety-related items that could impact safety-related items?
What criteria will the NRC apply with respect to determining what plant modifications will be l
required as a result of recalculations and/or review of i
calculations?
11.
To what extent will the NRC review the acceptability of
'!VA's revised diesel generator load sequencing calculations and 1
operating modes to assure sufficient diesel generator system capacity margin to. shut down the plant during a plant emergency?
To what extent will the NRC review the acceptability of TVA's battery systems to assure sufficient battery system capacity I
l margin to shut down the plant during a plant emergency?
l 12.
To what extent does the NRC intend to verify that problems l
identified by the DBVP have solutions and that necessary modifications have been v.dn grior to Sequoyah restart?
Which of the progre.ms, enumerated in the NRC handout (attached hereto) at the July 8, 1987 NRC/TVA meeting in Chatanooga, will be required by NRC to be completed prict to Sequoyah restart?
13.
What does the NRC plan tcjrequire from TVA to assure that the new design change control system is in place and working properly?
Is the NRC aware of the number of design changes and field changes that were made during the period ranging from mid-1996 through mid-1987 on the basis e,f waivers and/or variances fron tha new design change control program?
Will the NRC require prior to Sequoyah restart that TVA (A) verify that these changes are consistent with the plant baseline configuration, (B) assure that all impacts resulting from these reviews are assessed, and (C) assure that any resulting plant modifications are completed?
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14.
Does the NRC plan to require TVA to complete ongoing assessments and corrective actions concerning : ables prior to Sequoyah restart?
15.
What NRC actions are underway _ for the purpose of resolving questions concerning what constitutes acceptable sampling techniques?
What is the nature of outstanding questions regarding the adequacy of TVA's sampling practices?
When will l
any such ' questions be resolved?
l 4
l 16.
Will the NRC require that testing of. Sequeyah systems and components, undertaken between shutdown and restart, be-conducted I
in accord with standards, guides, test procedures, etc. that will j
be in effect at the time of restart?
17.
What is the impact upon the Sequoyah restErt schedule of the deficient conditions described in TVA's report,
'A REVIEW OF CAQ PROGRAM IMPLEMENTATION AT SEQUOYAH NUCLEAR PLAST 7" This report concluded:
The corrective action program is not being adequately implemented at SON and could not withstand an NRC inspection.
Unless expeditious corrective action is taken, the unit 2 startup schedule may be affected.
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