ML20006F379
| ML20006F379 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/16/1990 |
| From: | Warnick R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20006F378 | List: |
| References | |
| 50-445-90-03, 50-445-90-3, 50-446-90-03, 50-446-90-3, NUDOCS 9002270449 | |
| Download: ML20006F379 (3) | |
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APPEND,IX A-NOTICE OF VIOLATION h
~TUtElectric.
Dockets:
50-445/90-05 T
He J 50-446/90-03
- Comanche Peak. Steam Electric Station Permits
CPPR-126-s
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JUnits 1.and-2, Glen Rose, Texas CPPR-127
-During an NRC. inspection conducted on January 3 through February 6,
- 1990, violations of wnc' requirements were identified.
In accordance
'With the " General Statement'of Policy and Procedure for NRC if U.
Enforcement Actions," 10 CFR Part 2, Appendix C (1989), the-
- violations are-listed below:
A.
Criterion XVI'of Appendix B to'10 CFR Part 50 as implemented by Section116.0,; Revision;0, of,the TU Electric Quality Assurance
-Manual requires..that." Measures.shall=be ectablished to assure that conditions' adverse to quality,.
. are promptly 4
identified and corrected."
p Contrary;to-the:above, an error in Calculation 116345/6 :
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CS(B)-058, " Service WaterzIntake4 Structure-Exterior Wall Design," Revision 1,;which: Was.identifir.d by the NRC was not-adequately corrected.
The NRC, issued Open Item 445/8948-0-01; 446/8948-0-01 identifying'thatithe groundwater level-assumption E
'ofc780 feet in the above calculation;was;in conflict with-1 groundwater readings of:approximately 783; feet at two t
piezometers located next to'the'serviceiwater intake structure.
The applicant issued Change Notice 2 to the-base calculation
~
- which revised the assumed groundwater level to 783 feet'.
S
- However, the revised-groundwater level.of 783 feet was still inadequate in light of1the facts that.(1)-both of the local E
- piezometers read greater than 783 feet at some time duringithe 1988 monitoring program, (2) no margin was added-for'inFtrument error, and (3)/no consideration was made for the possible 7
- changes'in groundwater level over the 40-year service life of the intake structure.
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'This is a Severity Level IV-violation (Supplement II)
(445/9003-V-01; 446/9003-V-01).
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- B.-
Criterion XVI of Appendix B to 10 CFR Part 50 as implemented by Section 16 of the TU Electric Quality Assurance Manual requires that tr maures shall be established to assure that conditions u
adverse to quality are promptly identified'and corrected.
Furchermore, for significant conditions adverse to quality, the f}
measures shall assure that the cause of the condition is
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- determined land.that'adaquate correctiveLactions to preclude repetition are taken.
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. The Code of Federal Regulations 10 CFR Part 50.55(e) requires t
that the Commission be notified of each. deficiency found in construction,lwhich, were.it to have remained uncorrected, could have adversely affected the safety of operations and which-represents:
- (iv) A significant deviation from performance specifications-which will require extensive evaluation or repair to<
establish the adequacy of the structure system or component _
s to meet-the criteria and basis stated in the safety analysis, or to otherwise establish the adequacy of the structure,-system, or component to perform its intended safety function.
CPSES Nuclear Engineering and Operations Procedure NEO 9.01, Revision 4, Section 6.4.1.2 requires that evaluations for J
-reportability under 10 CFR 50.55(e).shall be documented on or attached to Reportability. Evaluation Forms (REFs) and shall provide justification as to why an adverse condition is or is not reportable.
Contrary.to the above, Plant Incident Report 89-243,.which
-identified the presence of foreign material in the containment-spray system which could have blocked a horizontal containment.
spray header and resulted in an unanalyzed condition during.
plant' operations, was inadequately reviewed for reportability,on SN-463.
As-a result:of this inadequate review, the root cause of>this condition and the generic.. implications were not-adequately addressed.
Furthermore, the corrective' actions were.
inadequate in'that the: applicant failed to properly examine other related areas that may have contained similar' debris.-
l
.This is a Severity Level IV violation (Supplement II)
-(445/9003-V-03).
Pursuant to-the provisions of 10 CFR 2.201, TU Electric.is hereby required to submit a written statement or explanation to the U. S.
. No lear Regulatory Commission,' ATTN: Document Control Desk, Washington, DC, 20555, with a copy to the Assistant Director for-i 1
--Inspection Programs, Comancho Peak Project Division, Off ce of j
Nuclear Reactor Regulation, within 30 days of the date of the letter transmitting this Notice..
This reply should be clearly marked as_a
" Reply to a Notice of Violation" and should include for each violation:
.(1) the' reason for the violation if admitted, (2) the
- corrective steps that have_beenLtaken and the results achieved, (3) the corrective steps that will be taken to avoid further z
violations, and-(4) the date when full compliance will be achieved.
- If.an ade~quateireply is not received within the time specified in k
- this Notice, aul order may be issued to show cauce why the license L-
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should not be modified, suspended, or revoked or why such other action as may be; proper should not be taken.
Where good cause'is
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- shown, consideration will be given to extending the response time..
1 FOR THE NUCLEAR REGULATORY. COMMISSION Sf/LlWi_l_-
I Dated.at Comanche Peak Site this 16th day of _ February 1990 i
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