ML20079J420
| ML20079J420 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire, 05000000 |
| Issue date: | 09/27/1983 |
| From: | Henry W DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20079J318 | List: |
| References | |
| PR-290, NUDOCS 8401240312 | |
| Download: ML20079J420 (9) | |
Text
- . l COVER SHEET j List of pages, forms, and attachments valid for this revision:
REVISION
- Page CS-1 9 Page 1 4 Page 2 8 Page 3 5 Page 4 1 Form 290.1 3 Enclosure 7.1 (Posted Notice) 2
- Enclosure 7.2 (50.55e Flow Chart) 4
- Enclosure 7.3 (Part 21 Flow Chart) 4 Enclosure 7.4 (NRC Report Format) 0
- Indicates pages affected by this revision.
! e -
t 8401240312 040113 PDR ADOCK 05000369 S PDR NUCLEAR REGULATORY COMMISSION REPORTING REQUIREMENTS TITL E*.
APPROVE D BY CATE REviloN DUKE POWER COMPANY QUALITY ASSUR ANCE MANUAL k-$90
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khN DESIGN ENGINEERING DEPARTMENT S 1e CS EFFECTIVE DATE:' OCT 101963
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Title:
NUCLEAR REGULATORY COMISSION REPORTING REQUIREMENTS
Purpose:
To establish the procedure for determining reportability and subsequent reporting of significant items to the Nuclear Regulatory Commission (NRC) as required by the following regulations:
- a. 10CFR21
- b. 10CFR50, Section 50.55(e)
Scope:
This procedure applies to all items identified during the design, construction, and l operation of a nuclear plant which are required to be evaluated for reportability to the NRC by Design Engineering.
Definitions:
REPORTABLE ITEMS -- Those significant items which have been evaluated pursuant to this procedure and the applicable regulations and are determined to be reportable to the Nuclear Regulatory Commission.
( POTENfIALLY REPORTABLE ITEMS -- Those" items which are of such significance that a
\ complete analysis may find them reportable.
RESPONSIBLE INDIVIDUAL -- The individual assigned the responsibility to evaluate a nonconforming item to determine potential reportability to the NRC.
- 1. RESPONSIBILITY 1.1 The cognizant Division Heads of the Design Engineering Department are responsible for problem evaluation assigned to their division.
1.2 The Quality Assurance Department has the responsibility to assure items determined reportable in accordance with this procedure are initially called in to the NRC.
1.3 The department to which a report is assigned has the responsibility to assure the written report is completed within the required time frame.
1.4 Persons detecting items or events which they believe to be reportable shall report such items to management under the provisions of this procedure.
- 2. PROCEDURE DURING DESIGN AND CONSTRUCTION PHASE 2.1 The attached flow charts (enclosures 7.2 and 7.3) should be used as guides in determining reportability to the NRC.
Entire Page Revised sECTioN Revision NE y DATE ggp g g 1382 PR-290 4
- 2.2 NCIs, Design Nonconformances When a deficiency that may be reportable is identified, the following steps must be followed within the indicated time frames:
2.2.1 As appropriate, a Nonconforming Item (NCI) or a Design Nonconformance (DNC) shall be generated if this has not already been done. The ireitiation of one of these forms establishes the
" Time Zero" point for the reporting schedulo.
2.2.2 After receipt of any of the above forms a prompt review shall be performed by the responsible individual. The Vice President, Design Engineering, Responsible Division Head, SRAL Division Head and Corporate QA Managei- shall be notified of any potentially reportable items in a timely manner. Notification should be accomplished by completing the " statement of problem" section of Form 290.1 and sending the stiginal to the Responsible Division Head and a copy to the othen specified above.
2.2.3 Upon receipt of the Form 290.1, the Division Head shall evaluate the problem for reportsbility and document his evaluation in the space provided. The determination of reportability must be made by a Division Head or Vice President. This cannot b_e delegated.
2.2.3.1 If evaluated as not reportable, the Division Head shall sign the
- form and forward the 290.1 form to the Corporate QA Manager or his designee.
( .
2.2.3.2 If evaluated as reportable, the Division Head shall sign the form and have it hand carried to the Corporate QA Manager or his designee. The Division Head, SRAL Division Head, and the Corporate QA Manager or their designees shall within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of completion of the evaluation make an iniUal telephone report to the Nuclear Regulatory Commission, Region II. This telephone report shall give a brief description of the item or event and a summary of any corrective action taken or to be taken. This call shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> even if all parties involved are not present.
2.2.3.3 In any case, within thirty calendar days of " Time Zero",
a decision must be made on reportability or the defi-ciency must be reported to the NRC as a70tentially Reportable Iteni. This telTphone report must be made no later than the thirty-first day as outlined in 2.2.3.2.
2.2.4 Quality Assurance shall record on Form 290.1 the NRC contact for potentially reportable and reportable items. In all cases Quality Assurance shall serialize, log, and distribute copies of the 290.1 form. Copies shall be sent to, as a minimum, Vice President Design Engineering,' SRAL Division Head, Steam Production Licensing for reportable and potentially reportable
- item, and the originator.
Entire Page Revised sECTloN "
9 DATE @2$M PR-290 8
2.2.5 Potentially Reportable items that are later determined by the
' Division Head to be not reportable may be cancelled. This shall be accomplished by the Division Head checking the cancel block on i the 290.1 form and signing the " Evaluated by" blank. The 290.1 form shall be sent to Quality Assurance who shall make the phone ,
cancellation to NRC and so note on the 290.1 form and process i copies as outlined in Step 2.2.4. The Division Head shall assure that the 290.1 form is delivered to QA before the reporting deadline.
2.2.6 For reportable items for which the written report is assigned to Design Engineering, the written report shall be approved by the Division Head. This report shall be written using the format given in Enclosure 7.4 and contain information required by 10CFR 21, Paragraph 21.21(3) even if the report is made as a 50.55(e) ;
event. The report must be delivered to the SRAL Division Head at least two (2) days prior to the due date established on the 290.1 form. The SRAL Division will assure the report is in the proper format and complete and shall submit the report to Steam Production Licensing Group one (1) day prior to the due date or l to the NRC in accordance with applicable regulations.
- 3. PROCEDURE DURING OPERATIONAL PHASE The procedure for evaluating and reporting deficiencies by Design Engineering '
on operating licensed units is identical to that for units in the design and f
construction phase with the following exceptions.
\
3.1 All phone contacts with the NRC will be made jointly by Steam Production, Design Engineering and Quality Assurance.
- 4. POSTING The notice shown in Enclosure 7.1 to this procedure shall be posted in a conspicuous position on any premise where activities subject to the regulation are conducted. In addition, the following must be available for any person desiring to see them, and the posted notice shall say where they are available.
4.1 The regulation in 10CFR Part 21.
4.2 The procedure adopted pursuant to the regulation in 10CFR21 (i.e. , this procedure).
- 5. RECORDS 5.1 Reports received by the Corporate QA Manager shall be serialized by project name, year, and sequential number. Records indicating the disposition of each potentially reportable item and of each reported item will be maintained by the Corporate QA Manager.
I Entire Page Revised s
oATE "N Revision "' 3 SEP 2 9 1982 PR-290 5
- 6. FORMS 6.1 290.1
- 7. ENCLOSURES 7.1 Posted Notice.
7.2 Flow Chart for 50.55(e) reportability.
7.3 Flow Chart for Part 21 reportability.
7.4 NRC Reporting Format r- -
l
(.
k caTE sEcrioN PR-290 REvlSloN 1 PAGE 4 3gp 3 , , .
Form 290.1 Revision 3 26155 iR8-82)
L POTENTIALLY REPORTABLE ITEM l
-- o QA Serial No.
Source Document (s)
Station / Project Serial No. (Optional)
, VN No.
NCINo. Unit DNC No.
Other Date Identified:
Statement of Problem I
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u.
l O l H z
w 2
E h
m l l
l By: r. _ Date:
Corporate QA Manager
( cc: OVP SRAL Division Head Other Eva uation:
9 E
D
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Conclusion:
Reportable Oyes No Applicable To: 50.55(e) CPart 21 Both
- Potentially Reportable (Evaluation incomplete) t Evaluated By: Date:
Potentially Reportable 1 tem Later Determined Not Reportable Cancel Evaluated By: Date:
i- Initial Telecon Report Made To: Formal Report Due: Cancellation Made To:
$ (Date)
, H 5 By: Assigned To: By:
o Submit Report To: Date:
@ Date:
a
s
' Procaduro PR-290
- c. ENERGY REORGANIZATION ACT OF 1974 UP"' 7d Act of October 11,1974 (Public Law 93-438)
I Section 206 NONCOMPLIANCE (a) Any individual director, or responsible officer of a firm construct-ing, owning, operating, or supplying the components of any facility or activity which is licensed or otherwise regulated pursuant to the Atomic Energy Act of 1954 as amended, or pursuant to this Act, who cbtains information reasonably indicating that such facility or activity or basic components supplied to such l
facility or activity--
(1) fails to comply with the Atomic Energy Act of 1954 as amended, or any applicable rule, regulation, order, or license of the Comission relating to substantial safety hazards, or (2) contains a defect which would create a substantial safety hazard, as defined by regulations which the Comission shall promulgate.
shall imediately notify the Comission of such failure to comply, or of such defect, unless such person has actual knowledge that the Commission has been adequately informed of such defect or failure to comply.
,,c (b) Any person who knowingly and consciously fails to provide the notice required by subsection (a) of this section shall be subject to a civil penalty in an amount equal to the amount provided by section 234 of the Atomic Energy
(' Act of 1954, as araended.
(c) The requirements of this section shall be prominently posted on the premises of any facility licensed or otherwise regulated pursuant to the Atomic Energy Commission Act of 1954, as amended.
(d) The Comission is authorized to conduct such reasonable inspections and other enforcement activities as needed to insure compliance with the pro-l visions of this section.
Regulations establishing procedures and requirements for the implementation of Section 206 of tne Energy Reorganization Act of 1974 have been promulgated by the Nuclear Regulatory Coanission in Title 10, Code of Federal Regulations.
[
Part 21 - Reporting of Defects and Noncompliance. Pursuant to 10CFR Part 21, implementing procedures for have been established as follows:
A copy of 10CFR Part 21 and the above listed procedures may be examined and reports of defects and noncompliance may be made by contacting:
at .
s ........................................
Procedure PR-290 Enclosure 7.2 .
Revision 4 Flow Chart 10CFR50.55(e) Reportability l Deficiency Identified I l
4 l: l Had it remained uncorrected, could have adversely affected l l l the safety of operations l l lYes l 4 l
l l Deficiency Represents a l Yes l l Significant Breakdown in l ,
l l the QA Program l l l fNo l l l l l Deficiency is a significant deficiency in final design l Yes I l l as approved and released for Construction such that the l :l g l l design does not conform tg t_he criteria and bases in l l s l l SAR or Construction Permit l l fNo l l l l l Deficiency is a significant deficiency in construction, l l l l significant damage, or a significant deviation from performance l l l l l l l: Nol or specifications redesign to meet which will require criteria and basisextensive in SAR or evaluation, Construction repair, l l l l Permit or to otherwise establish the adequacy of the item to meet l l l l its intended Safety Function l l l l l l l 1 l l Evaluation Not l l l l l Complete Within l :l 4 l l 30 Days l l:
l l l 1 4 4 l Item Not l l Report to NRC Within l lReportablel l 24 Hours l l
4 l 30 Day Formal Report l
. _ _ . . - ~
- - . _ - _ = _ _ _ .
Precsdure PR-290 Enclosura 7.3 i Revision 4
)
Flow Chart 10CFR21 Reportability I Deficiency Identified I l
4 l Deficiency in Security which, l yes l on the basis of an evaluation, l ;y l could create a substantial l l l safety hazard. l l I
No l
l l Failure to comply with Atomic Energy l l l Act of 1954, as amended, or any l l l applicable rule, regulation, order l l l or license of the NRC, specifically I I Yes l including the Duke operating license l :l l and supporting documents such as the l l l SAR and subsequent submittals to the l l l NRC. On the basis of an evaluation, l l l deficiency could create a substantia 1l l l safety hazard. l l
' - No
(' l l
l
+ l l
" l Defect in a Basic Component l l: l i
l lYes l l +
I l l Evaluation Not l 1:
l l Complete Within l :l l l 30 Days l l l l 4 +
l Item Not l l Report to NRC Within l lReportablel l 24 Hours l l
1 i
I 5-Day Formal Report l l PMD Project Manager l l 1 notifies affected l
. l l client (s). (telecon)l 4
l PMD Project Manager l l notifieds affected l
. I clients. (formal l l report) 1
- _ - . . _ , _ - _ .