ML20138H524

Applicant Exhibit A-66,consisting of Rev 5 to Procedure PLP-02, Reporting Design & Const Deficiencies to NRC,

ML20138H524
Person / Time
Site:	South Texas
Issue date:	08/06/1985
From:	Powell M HOUSTON LIGHTING & POWER CO.
To:
References
OL-A-066, OL-A-66, NUDOCS 8510290064
Download: ML20138H524 (25)

Text

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SUMMARY

OF REVISIONS eace No. suottcT REPORT 1hG DESIGN AhD C0h5TRLCTION

-02 DEFICIENCIES TO NRC "85 ppr m "O ' Ouality Pelated - Yes arvisioN DEstmetioN NOlg}

O Changed procedure number from PEP-4.01 to PLP-02.changedthel I Nhtih deficiencies solely to the Team Leader, Nuclear Licensing; removed distinction between site and home office handling of deficiencies and clarified engineering's role in the evaluations.

1 Complete revision to procedure.

2 Change to Section 5.6 changing Project Manager to Manager, South Texas Project. Editorial changes to Attachment 9.3.

Revision to Attachment 9.5.

3 Changed " incident" to deficiency. Added new sections 4.2.10, 5.4, 6.5, 6.6 and re-renumbered existing Secticns. Added new Attachments 9.8 and 9.9. Attachments 9.5 and 9.7 were revised.

4 Changed Manager, STP Site to Deputy Project Manager in

, Attachment 9.8 on Page 23. Added Deputy Project Manager Attachment 9.9, page 24.

5 Changed Executive Vice President, Nuclear to Group Vice l

President, Nuclear in Sections 4.2.9, 4.3.4 and 5.8. Deleted reference to Vice President, Nuclear Engineering and Construction l

in Section 5.8 since this position no longer exists. Added the word boundary to attachment 9.5, item B.1 to identify "the integrity of the reactor coolant pressure boundary." These changes are editorial in nature, mucLtan AtCULATORf COMMinton

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' ' " ' ' can essao REPORTING DESIGN AND CONSTRUCTION 05-21-85 DEFICIENCIES TO NRC 1.0 PURPOSE 1.1 To establish the procedure for identifying and evaluating conditions which could potentially affect the safety functions of STP and for reporting deficiencies, defects and noncompliance to NRC in accordance with 10 CFR 50.55(e) and 10 CFR 21.

2.0 SCOPE 2.1 This procedure applies to conditions identified during the design, engineering, and construction phases of each unit of the STP, prior to the issuance of the operating license for each respective unit.

2.2 This procedure also applies to conditions reported to STP by its architect-engineers, constructors, suppliers and any other contractors or consultants.

3.0 REFERENCE DOCUMENTS 3.1 NRC I&E Information Notices 80-28, " Prompt Reporting of Information in Accordance with 50.55(e)." 79-30, " Reporting of Defects and Noncompliance, 10 CFR Part 21."

3.2 10 CFR 50.55(e) - Attachment 9.1 3.3 10 CFR 21 3.4 NRC I&E Inspection Manual, " Guidance - 10 CFR 50.55(e) Construction Deficiency Reporting", 4-01-80.

3.5 Corporate Procedure, Handling of Conditions Potentially Reportable under 10CFR21 3.6 Reporting of Safety-Related Defects and Non-Compliancies -

Attachment 9.2 4.0 DEFINITIONS 4.1 10 CFR 50.55(e) Definitions - As used in this procedure 4.1.1 Significant - Having an effect or likely to have an effect on, or influence, the safe operation of the facility in an adverse manner.

4.1.2 Extensive - Expenditure of resources (time, manpower, or money) to a degree disproportionate with the original design, test or construction expenditure.

4.1.3 Final Design - Denotes those drawings, specifications, or other engineering documents that have been reviewed, approved and released for fabrication, installation or construction.

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! REPORTING DESIGN AND CONSTRUCTION 05-21-85 ,

4 DEFICIENCIES TO NRC i

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4.1.4 Potentially Reportable Deficiency - A deficiency in design or construction which could be significant but for which additional time is required (in excess w 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) to detennine if the criteria for a reportable deficiency have been met.  !

4.1.5 Reportable Deficiency - A deficiency in design or construction, which, were it to have remained uncorrected, could have adversely affected the safety of operations of the nuclear power plant at anytime throughout the expected lifetime of the

^

plant, and which represents at least one of the following criteria:

(1) A significant breakdown in any portion of the Quality j

Assurance Program conducted in accordance with the '

requirements of 10 CFR 50, Appendix B.

(ii) A significant deficiency in final design as approved and

)i released for construction such that the design does not

" conform to the criteria and bases stated in the Safety T Analysis Report (SAR) or construction permit. /

(iii) A significant deficiency in construction of or signifi-cant damage to a structure, system, or component which

' will require extensive evaluation, extensive redesign, or extensive repair to meet the criteria and bases stated in the Safety Analysis Report or construction permit or to otherwise establish the adequacy of the structure, system, or component to perform its intended safety function.

c (iv) A significant deviation from perforr:ance specifications 1 which will require extensive evaluation, extensive redesign, or extensive repair to establish the adequacy of the structure, system, or component to meet the i

criteria and bases stated in the Safety Analysis Report i or construction permit or to otherwise establish the adequacy of the structure system or component to perform i

its intended safety function. j 4.2 10 CFR 21 Definitions - As used in this procedure 4.2.1 Besic Component - A nuclear power plant structure, system, ,

component, or part thereof, necessary to assure

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(1) The integrity of the reactor coolant pressure boundary; g ,

1 (2) The capability to shut down the reactor and maintain it in a safe shutdown condition; g I M2/F002/a J

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REPORTING DESIGN AND CONSTRUCTION DEFICIENCIES TO NRC 05-21-85, (3) The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to those referred to in 10 CFR 100.11.

In all cases, the term " basic component" includes design, inspection, testing, or consulting services, important to safety, that are associated with the component hardware, whether these services are performed by the component supplier or others.

Those plant structures, systems, or components, or parts thereof, at a minimum, which are identified as either Safety Class 1, 2, or 3 or Seismic Category I, are basic components.

4.2.2 Commercial Grade item - An item that is (1) not subject to design or specification requirements that are unique to facilities or activities licensed by NRC, and (2) used in applications other than facilities or activities licensed by NRC, and (3) able to be ordered from a manufacturer / supplier on the basis of specifications set forth in his published product description (e.g., a catalog).

A comercial grade item becomes a basic component after receipt when it is dedicated (designated for use as a basic component) by the recipient.

4.2.3 Deviation - A departure from the technical requirements of a procurement document for a basic component.

4.2.4 Procurement Document - A contract which defines the requirements which the facility or basic component must meet in order to be considered acceptable by the purchaser. This includes specifications, purchase orders and other documents that establish the requirements for purchaser acceptance and includes code requirements, drawings and procedures that are referenced as part of the procurement document.

4.2.5 Delivery - Transfer of control of a basic component. Delivery occurs upon acceptance of a basic component made subsequent to a test or inspection which takes place within a reasonable time after receipt. If no test or inspection is perfomed within a reasonable time, the basic component will be deemed to have been delivered. If a component is rejected on the basis of a deviation identified during a receipt test or inspection, delivery has not occurred.

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REPORTING DESIGN AND CONSTRUCTION 05-21-85 -

DEFICIENCIES TO NRC 4.2.6 Substantial Safety Hazard - A loss of safety function to the extent that there is a major reduction in the degree of protec- -

tion provided to public health and safety (including employee health and safety). Criteria which are appropriate for the detemination of the creation of a substantial safety hazard include:

- Moderate exposure to, or release of, radioactive effluents or materials;

- Major degradation of essential safety-related equipment; I

- Major deficiencies in design, construction, use of, or management controls for ifcensed facilities or material.

4.2.7 Defect -

(1) A deviation in a basic component delivered to a purchaser for use in a facility or activity subject to 10 CFR 21, ,

if, on the basis of an evaluation, the deviation could -

)

create a substantial safety hazard; or (2) The installation, use, or operation of a basic comperent containing a defect as defined in (1) above; E (3) A deviation in a portion of a facility subject to the con-struction permit requirements of 10 CFR 50, provided the deviation could, on the basis of an evaluation, create a substantial safety hazard and the portion of the facility containing the deviation has been offered to the purchaser for acceptance; g (4) A condition or circumstance involving a basic compenent

' that could contribute to the exceeding of a safety lir:it, as defined in the technical specifications of a license for operation issued pursuant to 10CFR Part 50.

4;2.8 Nonenmpliance - The failure of a basic component activity, or facility to comply with the Atomic Energy Act of 1954, as amended, or any applicable rule, regulation, order or license of the NRC relating to substantial safety hazard.

4.2.9 Responsible Officer - The Group Vice-President, Nuclear l is that individual in HL&P who is vested with executive authority over the activities subject to 10 CFR 21. ,

4.2.10 Responsible Individual - Those individuals within HL&P who may become cognizant of 10CFR21 reports made by STP architect-engineers, constructors, suppliers and any other W2/F002/a _

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' * mavaissuto REPORTING DESIGN AND CONSTRUCTION DEFICIENCIES TO NRC 05-21-85.

s contractors or consultants. See Attachment 9.8 for a listing of STP responsible individuals.

4.2.11 Constructing or Construction - The design, manufacture, fabrication, placement, erection, installation, modification, inspection, or testing of a facility or activity, and consult-ing services related to the facility or activity that are im-portant to safety.

4.3 Procedure Definitions 4.3.1 Sionificant Deficiency - An event or condition which has an effect or is likely to have an effect on, or influence, the safe operation of the facility in an adverse manner.

4.3.2 Initial Evaluation - Evaluation of a significant deficiency to determine if it is a reportable or potentially reportable deficiency under 10 CFR 50.55(e) or if there is a need to consider it further under 10 CFR Part 21.

4.3.3 Technical Evaluation - The technical, including safety, evalua-tion of a significant incident to determine if the criteria for reportable deficiency under 10 CFR 50.55(e) or a defect or non-compliance under 10 CFR 21 are met. The technical evaluation is performed subsequent to the initial evaluation.

4.3.4 Incident Review Committee (IRC) - The project committee respons-ible for concucting the initial evaluation and subsequent tech-nical evaluation of significant deficiencies. Unless an incident review is conducted by a committee under the direction and supervision of the Group Vice President, Nuclear as a minimum, the IRC shall consist of the following members or their designees:

1. Project Licensing Engineer (Chairman)

2. Project QA Supervisor

3. Cognizant Supervising Project Engineer, Houston Engineering 4 Other cognizant individual (s) as designated by the Chairman.

4.3.5 Notification - A telephone, telegraphic or verbal report.

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REPORTING DESIGN AND CONSTRUCTION 05-21-85 DEFICIENCIES TO NRC 5.0 RESPONSIBILITIES i

5.1 Originator 5.1.1 Any HL&P employee, except those individuals carrying out their responsibility as required by Section 5.4, who becomes aware of a condition which he or she believes constitutes a substantial safety hazard or a significant deficiency has the responsi-bility to prepare a Deficiency Evaluation Form (DEF) in accordance with this procedure. A DEF must be prepared even u'ider circumstances where the information is known to be covered by a NCR.

5.1.2 The originator has the responsibility to provide accurate and sufficient data or information to the extent known.

5.2 Responsible Supervising Project Engineer (SPE) 5.2.1 The SPE is responsible for reviewing deficiencies doeurented by a DEF and making recomendations relative to their significance to the Manager, Engineering. )

i 5.3 Manager, Engineering 5.3.1 The Manager, Engineering is responsible for perfoming prelim-inary screening of documented deficiencies to determine if they are significant deficiencies.

5.3.2 The Manager Engineering is responsible for notifying the IRC Chairman of significant deficiencies.

5.3.3 The Manager, Engineering is responsible for technical interface with the major contractors regarding technical support in evaluation of 10 CFR 50.55(e) and 10 CFR 21 items.

5.4 Responsible Individuals 5.4.1 Those designated responsible individuals (see attachment 9.8) are responsible for imediately informing the IRC Chairman once j they become aware that any STP supplier, contractor or consultant has notified the NRC of a 10CFR21 item that may be applicable to the STP.

5.4.2 Those individuals responsible for the interface with the STP architect-engineer and/or NSSS supplier are responsible for imediately informing the IRC Chairman once they become aware

• that the STP architect-engineer and/or NSSS supplier has notified the NRC, or HL&P of potentially reportable deficiencies. See attachment 9.9.

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DEFICIENCIES TO NRC I

5.5 Incident Review Committee (IRC) 5.5.1 The IRC is responsible for conducting the initial evaluation of significant deficiencies and, if applicable, for initiating and reviewing the technical evaluation.

5.5.2 The IRC Chairman is responsible for drafting the written reports to NRC.

5.5.3 The IRC Chairman is responsible for publishing minutes of each 1

IRC meeting. Minutes shall include, as a minimum, identification of participants, listing of deficiencies considered, and an explanation of findings, as applicable.

5.5.4 The IRC ~ Chairman is responsible for notifying the NRC of poter.tially reportable deficiencies and reportable deficiencies. The initial notification (if appropriate) shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the time that the IRC Chairman is informed that there exists a significant deficiency.

5.5.5 The IRC Chairman is responsible for maintaining files pertaining to 10 CFR 50.55(e) and 10 CFR 21 evaluations.

5.5.6 The IRC Chairman is responsible for notifying the originator of the disposition of those items referred to the IRC. This may be accomplished by sending the originator a copy of the IRC meeting minutes.

5.6 Manager, Nuclear Licensing 5.6.1 The Manager, Nuclear Licensing is responsible for reviewing the IRC's completed evaluations and the written reports before submission to the NRC.

5.7 Manager South Texas Project 5.7.1 The Manager, South Texas Project ensures that appropriate resources are made available to assure that evaluations and reports are completed in a timely manner.

5.8 Group Vice-President, Nuclear 5.8.1 The Group Vice-President, Nuclear is responsible for submitting the written reports to the NRC.

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MOUSTON UGHTING S POWER COMPANY PROC NO. RE V. No SOUTH TEXAS PROJECT PROCEDURE MANUAL PLP-02 5 TsTLE PAGE op PROJECT LICENSING PROCEDURE 8 24 5"*" cavEissvEO REPORTING CESIGN AND CONSTRUCTION DEFICIENCIES TO NRC 05-21 l' 6.0 PROCEDURE 6.1 Any HL&P Employee who identifies an event or condition that may be a significant deficiency, or who obtains infomation of such an event or condition, shall prepare a Deficiency Evaluation Form (DEF)

(Attachment 9.3) and forward it directly to the responsible Supervising Project Engineer (SPE) in Engineering. If the originator is unsure who the responsible SPE is, he shall forward it directly to the Manager, Engineering for distribution. The DEF should be prepared in as short a time frame as possible, and should include sufficient information to facilitate preliminary assessment.

6.2 The responsible SPE shall log in the DEF and confirm that the DEF is accurate and contains sufficient information to facilitate preliminary assessment. He shall then review the DEF expeditiously to determine if it should be recomended for IRC review. If the SPE determines that a reported condition or event does not constitute a significant deficiency he shall document the basis for that determination on the DEF.

6.2.1 If recceended for review by the IRC, it is so noted on the DEF

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and forwarded (hand-carried) to the Manager, Engineering.

6.2.2 If not recomended, it is so noted on the form and copies sent to:

1) Originator

2) Manager Engineering

3) IRC Chairman 6.2.3 In either case, DEF's should be processed expeditiously and without delay to reach the Manager Engineering as soon as possible, 6.3 If the Manager, Engineering is not available, the responsible SPE shall act for the Manager to accomplish the activities described in j 6.4.

6.4 For a DEF which the SPE has recomended for IRC review, the Manager. l l Engineering shall imediately evaluate the DEF to detemine if the  !

condition or event reported constitutes a significant deficiency. If  !

he detemines that a significant deficiency exists he shall send the DEF to the IRC for review.

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05-21-85 , l REPORTING DESIGN AND CONSTRUCTION

. DEFICIENCIES TO NRC 6.4.1 If the DEF is to be reviewed by IRC, it is so noted on the DEF and immediately forwarded (hand-carried) to the IRC Chairman. _

6.4.2 If the DEF is not to be reviewed by IRC, it is so noted on the fom along with an appropriate explanation and copies sent to:

1 Originator 2 IRC Chairman

3) Responsible SPE 6.5 In the event that a responsible individual STP, he (see atta notified the NRC of a IOCFR21 item that may be applicable to shall imediately so inform the IRC Chairman.

In the event that any of those individuals responsible for the 6.6 interface with the STP architect-engineer and/or NSSS supplier becomei i he aware that the STP architect-engineer and/or NSSS shall imediately so infom the IRC Chairman.

6.7 The IRC Chaiman, upon notification by the Man of a 10CFR21 item reported by a vendor (per Se:

Section 6.6; shall initiate an IRC meeting.

6.7.1 The IRC deficiency significant shall conduct an initial is a potentially evaluation reportable to determ deficiency, a reportable deficiency, or not reportable, under provisions of consider the deficiency under the proviskns of 6.7.2 The detemination of the IRC shall be documented on an IRCMinute Evaluation Form (Attachment 9.4). A copy of the IRC shall be available as soon as practicable.

Evaluation Fom shall be sent to the originator.

6.7.3 If the IRC determines that a reportable or potentially h reportable deficiency exists the IRC Chaiman shall notify t e NRC. The initial evaluation and notification to NRC shall b accomplished within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from the time that the IRC Chairman was informed that a significant deficiency exists.

The notification to NRC must be documented in telephone minutes.

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6.8 If the NRC is notified of a potentially reportable deficiency or the IRC has determined that 10 CFR 21 might be applicable, the IRC Chaiman shall initiate a technical evaluation.

6.8.1 The technical evaluation will be conducted to make a final determination of reportability under 10 CFR 50.55(e) and to determine reportability under 10 CFR 21.

6.8.2 The IRC Chairman shall assign a cognizant group with expertise relsted to the incident to perfom the technical evaluation.

6.8.3 If the technical evaluation as reviewed by the IRC indicates the matter is reportable, the IRC Chairinan will prepare a written report per Section 7.0 for submittal to the NRC.

6.8.4 The written report shall contain, as a minimum, the known information required by 10 CFR 50.55(e). If the determination is made that the incident is reportable under 10 CFR 21, the information required by 10 CFR 21.21 shall also be included.

6.8.5 If the technical evaluation indicates the matter is not report-able, the IRC Chaiman will convene the IRC to verify the find-ing of non-reportability. Meeting minutes shall be available  ;

as soon as practical, and shall document the determination with justification.

6.8.6 If the NRC was notified of a potentially reportable deficiency, but the technical evaluation determines that the deficiency is not reportable, the technical evaluation will document such determination with justification. Once the IRC has concurred that the item is not reportable, the IRC Chairman shall notify the NRC, document the notification on the IRC Evaluation Fem

and prepare a written report to inform the NRC of the results of the evaluation.

6.8.7 Nomally, if the technical evaluation cannot be completed on a l schedule consistent with the preparation of the written report, the deficiency is considered reportable and an interim report shall be submitted to NRC per Section 7.0. An item can be maintained as potentially reportable after the 30 day report. .

if the technical evaluation is ongoing and is expected to be I routinely completed soon after the 30 day period. In such a I case, a followup report will be submitted to the NRC upon

completion of the technical evaluation.

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l l 6.9 For reportable or potentially reportable deficiencies that are also determined to be reportable under 10 CFR 21, NRC shall be notified by i including the appropriate information in the report described in Sec-  ;

i tion 7.0. However, the Notification process and other subsequent i requirements of this procedure shall be invoked as if the defect o*

l noncompliance were a reportable deficiency under 10 CFR 50.55(c). For deficiencies determined reportable under 10 CFR 21 but not otherwise reportable under 10 CFR 50.55(e), the NRC shall be notified in i accordance with 10 CFR 21. 10 CFR 21 requires initial notification

within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of completion of IRC's detemination that 10 CFR 21 applies, i

6.10 The IRC shall also be convened from time to time by the IRC Chairman to review those DEF's that Engineering determined were not significant. The purpose of this review is to provide added assurance that all significant items are being considered by the IRC. Meeting i

minutes should include a listing of those DEF's considered and conclusions reached.

7.0 REPORTS TO NRC

! 7.1 For those deficiencies determined to be reportable under 10 CFR 50.55(e) the written report will be submitted to NRC within 30 calendar days of the initial notification to NRC. This report shall contain the pertinent elements identified in Attachment 9.6. For these items called into the NRC as potentially reportable but

, subsequently determined not to be reportable, verbal notification must be made to the NRC within 30 calendar days followed by written confirmation.

.! 7.2 For those deficiencies determined to be reportable under 10 CFR 21 but i not under 10 CFR 50.55(e), the written report shall be submitted to j NRC within 5 days of the completion of IRC's determination that 10 CFR

21 applies.

. 8.0 MAINTENANCE OF RECORDS r 8.1 In addition to any other files maintained by applicable procedures, a file of each deficiency evaluated by an IRC subsequent to the ',

effective date of this procedure shall be maintained under the

cognizance of the IRC Chairman. -

i 8.2 Each file shall contain the documentation associated with the

! deficiency including the IRC Evaluation Form with all supporting j documentation, copies of minutes of IRC meetings, and all copies of

, written reports to hRC.

1 i 8.3 A copy of those items described in 8.2 shall be forwarded to Records Management.

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DEFICIENCIES TO NRC 05-21-85 ,

9.0 ATTACHMENTS 9.1 10 CFR 50.55(e) 9.2 Reporting of Safety-Related Defects and Non-Compliance 9.3 Deficiency Evaluation Form 9.4 IRC Evaluation Fom 9.5 10 CFR 21 Evaluation Form 9.6 Contents of Written Report 9.7 Procedure Flow Chart 9.8 List of Responsible Individuals 9.9 List of Individuals responsible for the architect-engineer /NSSS supplier interface W2/F002/a s

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" " ca n issuso REPORTING DESIGN AND CONSTRUCTION 05-21-85 DEFICIENCIES TO NRC ATTICHMENT 9.1 - 10 CFR 50.55(e) Pace 1 of 1 te)(1) If the peruut is for construc* (3) The holder of a construction er tion of a nuclear poser plant. the permit shall within 34 hours3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> cottfy holder of the perTnat shall nottfy the the appropriate NucTear Regulatory Commaston of each deficiency found Commission Inspection and Enforce-in design and construction. which. ment Regional Officq of each reporta-were at to hase remained uncorrected.

could have affected adversely the ble(3)deficiency. - *IThe holder of 70$2ructIon safety of operations of the nuclear permit shall also submit a wntten report on a reportable deficiency fhe up tad 11 e tme o e a .

within tfurty (30) days to the appro.

untch represents: prtate NRC Regional Office shown in (t) A significant breakdosTt in any Append!n D of Part 20 of this chapter.

portion of the quality nasurance pro- Coples of such report shall be sent to gram conducted in accordance sith ** the Director of 1rtspection and En.

the requ rements of Appendix B to fortement. US. Nuclear Regulatory this part; or Comtnaston Washington. D.C. 205M.

(11) A s:gnifleant defletency in finaj The report shall include a desertation desfgn as approved and released for of the deficiency. an analysis of the cortstruction such that the design does safety implications and the corrective not conforTn to the criteria and bases action takert, and tuffiefent trtforma.

stated in the safety artalysJ report or tion to permit analysts and evaluation corJtruction per=ut; or of the defletency and of the correctise (L11) A signt!!carit deficiency in een-struetton of or sismficant damage to a action. If sufficient information is not svadable for a defintttte report to be structure. system. or component thtch st11 require extensive evaluattors. ex- subrnatted sithin 30 days. an intenm tensive redes:gn.or extensive repair to report containing all available infor.

mation shall be filed. together with a meet the cr'.terta arid bases stated in statement as to when a complete the safety ana!Tsts report or construe. '

Lion perTr.it of to othervue estabilah report stil be fUed.

the adecuacy of the structure, system. (4) RernedJa! action may be taken or component to perform its Intended both pnor to and af ter notification of safety function or the Divuton of Inspection and Eri-tiv) A sigTuf! cant deviation from per' fortement subject to the ruk of subae-formarite speClficattorJ thich will re* Quent disapprVtal of such action by cuire entensive evaluation extensive the Commaston.

redesign. or extensive regalt to estab-ILsh the adequacy of a structure, system. or ecmponent to meet the ert-tens and bases stated la the safety analy33 report er construct! ort perTE!!

of to otherwise estab!Lah the adequacy of the structure, system. or component to perform lla ,tatended safety func.

uon. .

O W2/F002/a

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• AOC NO. %w No HOU$TCN LIGHTING O POWE A COMPANY SOUTH TEXAS PROJECT PROCEDURE MANUAt.

PLP-02 5 PROJECT LICENSING PROCEDURE 14 24 .

'"" REPORTING DESIGN AND CONSTRUCTION

• *" '55 ' '

05-21-85 DEFICIENCIES TO NRC ATTACHMENT 9.2 - 10 CFR 21 Pace 1 of 2 10 CFR 21 " Reporting of Defects and Noncompliances" See the following page for a statement of the provisions of 10 CFR Part 21.

.r .

W2/F002/a i

HOUSTON LIGHTING 6 FOWE A COWANY #ACC No. RE v. p.o SOUTH TEXAS PROJECT PROCEDURE MANUAL PLP-02 5 T4TLE

• ACE OF PROJECT LICENSING PROCEDURE 15 24 Sv 5d CT DATEt$$vt0 REPORTING DESIGN AND CONSTRUCTION DEFICIENCIES TO NRC 05-21

• Reporting of Safety Related Defects and Non Compliances Attachment 9.2 e.oww. ser e.c. . so*'"

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76TLE pact op PROJECT LICENSING PROCEDURE 16 24

oare issuso REPORTING DESIGN AND CONSTRUCTION DEFICIENCIES TO NRC 05-21 I ATTACHMENT 9.3 Page 1 of 2 Otticit=cv tvaLuattom roens m - e,..r - ..eero.i.. ~ .e,.eu e.e. '***"'*****W-se israt% is Ias was seed heae ewisused as se saae. ares as Dreisammass.

pwsaet is PLP-41 The m.t.sieri swd p.e . sesweew e esusapuan -

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HOUSTON UGHTING G POWE A COMPANY #ftOC NO. 5:E V. NO SOUTH TEXAS PROJECT .-

PROCEDU;1E MANUAL PLP-02 5 TITLE pAGE OF PROJECT LICENSING PROCEDURE 17 24 5 " 5

REPORTING DESIGN AND CONSTRUCTION ^'5'55

DEFICIENCIES TO NRC 05-21-85, ATTACHMENT 9.3 Page 2 of 2 INSTRUCTION FOR COMPLETING A DEFICIENCY EVALUATION FORM LINE NO. INSTRUCTION .

1 The responsible SPE should assign and record fom and revision number; enter date report received.

2 Record the unit number (s) affected. Record the safety class and seismic category of the system, structure, or component.

3 Give a brief description of how the deficiency was discovered.

Reference any deficiency related documents.

4 Record the title of the governing documents.

5 Record the requirement stated in the governing documents.

6 Describe the deviation and hazard as accurately and completely as possible.

7 Signature of the initiator and the date the form was prepared.

8 The SPE marks the appropriate "yes" or "no" block, signs and dates the DEF. Provide a short discussion of the basis for the determination. Distribution is made in accordance with Section 6.2.

9 The Manager. Engineering, marks the appropriate "yes" or "no" block, signs and dates the DEF. Provide a short discussion of i the basis for the determination. The Manager, Engineering may simply concur with the reason provided by the SPE.

Distribution is made in accordance with Se: tion 6.4.

1 Steps 2 through 7 apply to DEF originator.

W2/F002/a e

HOUSTON LIGHTING & POWra COMPANY 88 toc No. atv No.

• SOUTH TEXAS PROJECT PROCEDURE MANUAL PLP-02 5 TITLE PAGE Ce PROJECT LICENSING PROCEDURE 18 24 5"

REPORTING DESIGN AND CONSTRUCTION **"'"'

DEFICIENCIES TO NRC 05-21-85 ATTACHMENT 9.4 Page 1 of 2 IRC EVALUATION FORM let tyc ontre= roen la: Catawi oAtt .

sattr ers:stette= or In: :!=t: .

thitts are:sta!!t t'T Cf'Isminatt0* (leeress.ggr,)). gr$ It!ctFI !!47 no pr .p t:s There entsts e oef tetency in aestg9 er constructton N/A E.2 Deffeteacy nomstats a stp9f ficaet P (t) Irvand:=a ta say poettoa of the CA Prog *am (per IC;FA50. As:eadts 8) .

Co (11) Defitf eacy in (Ital destga as neceoved sad releases fe' coast %ction (does not coafsm to SA8 or CP) .

ce (111) Dee teteacy in toistructica er coast %ctica samage w*1cm evt. ores esteastve evaluation.

n cesiga er escair .

Ce (1,) Deviatice from piafemsace specificattoes weite res/res esteastre evatwatten.

redestga er repate .

Awe Were it to rowin wacoerviiid could have adveesely affected the safety of operations .

The inciseat is:

Det reportable vader 100FR50.55(e)

Reportante under 10CFt50.llfe) (8eportatt11ty critects see set)

Peteattally reportable mader IC*FRSO.llfe) (Fur ther evaluattoa is necessary to determine if reportabiltty criteria are set)

This incident:

Att be fu ther r evaluated with respect to 10CFR21 (Use Attachawat 9.$)

heed not be further evaluated with respect to 10CTR21 jIo EnGI M a

SOUTH TEXA$ PAOJECT PROCEDURE MANUAL PLP-02 5 T6TLE 7t.G E CF PROJECT LICENSING PROCEDURE 19 24

. REPORTING DESIGN AND CONSTRUCTION DEFICIENCIES TO NRC 05-21-85 ATTACHMENT 9.4 Page 2 of 2 ht[ n?'ff!CA?!C%

Date . Itse .

IP6 t v i d.a i Po t t f i e d 41 48 hottfieg by .

of N6F Fin A; ef e*8' At!,' 1t? !f'f f*'n8'f ?is fl0!fe? ? $$ fe l); gg .

Theet entltt 4 8ef1Cle*Cy in deligi 0F C0*ltPWCt109 Deficieacy reemeats a sigaf ficaat (t) Seests == te say pe*tten Of the CA Pregeam (Per IC;FB50 Acte sta B)

On f (ii) De'9 Cleaty7p ffPol desiga at ogC*ceed ead feteeled for CO*ltrbetten Cs (doel Pet Comform to SAR Or CP) .

(iii) Deficie*Cy7P Co*ltPVCtica e' C0*ttfvCt'0* de*dte e itP regatret esteative evaIwat10n. Fedeltgm 0F repate C8 liv) Deviet90a Trca pe*fC mate specif ttat10es unich reewires este* live eveIwot10P, Pedeliga 0F repatr

,,e.e ,t ,0 - , J ii,eu e. 0wie ..we . ,ve. ei, .ffened t e

$48 ety Of 0$e'etteet Tre , entsts a copertante deffeteacy

. Attet* all nocellery supp0*ttag detvavatatten .

Comats t het notificat10n (if regwtred er step 6.6.6)

Date itse lesteid.si notified at h80 N0tified by .

O e .

&N. bee' W R Nte Seelewed Reasser, n. clear Liceanieg Gate I

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F stp %94 ft 831 HOUSTON Ll2HTIN3 O POM2 COMPANY #CCC. Peo. :t v. No SOUTH TEXAS PROJECT PROCEDURE MANUAL PLP-02 5 TiTLg

• AGE 08 PROJECT LICENSING PROCEDURE 20 24 5' 'd :'

REPORTING DESIGN AND CONSTRUCTION

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DEFICIENCIES TO NRC

• • '[5 21 85 - - -

ATTACHMENT 9.5 Pace 1 of 1 innn e.e... .

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see na a s2 MOUSTON LIGHTING B PCAt2 CcMPANY 'ACC No atv No SOUTH TEF. As PROJECT PROCEDU2E MANUAL PLP-02 5 t

T*TLE eacs e, PROJECT LICENSING PROCEDURE 21 24

' " **55"'

REPORTING DESIGN AND CONSTRUCTION DEFICIENCIES TC NRC 05-21-85 ,

ATTACHMENT 9.6 Pace 1 of I CONTENTS OF WRITTEN REPORT TO NRC If it is detemined that the deficiency is reportable under 10CFR50.55(e), the written report will contain all of the information, to the extent known, required by regulation. The report shall include a description of the deficiency, an analysis of the safety implications and the corrective action taken, and suffi-cient information to pemit analysis and evaluation of the deficiency and of the corrective action. If sufficient infomation is not available for a definitive report to be submitted within 30 days, an interim report containing all available info mation shall be filed, together with a statement as to when a complete report will be filed.

If it is detemined that Part 21 is applicable, then the report shall contain the following infomation to the extent known:

(i) Naee and address of individual infoming the Commission.

(ii) Identification of the facility and the basic coeponent which contains a defect or fails to comply.

(iii) Identification of the fim supplying the basic component which contains a defect or fails to comply.

(iv) Nature of the defect or failure to comply and the safety hazard which could be created.

(v) Date on which information on the defect or failure to comply was obtained. (i.e., date the determination of reportability pursuantto20CFRPart21wascorpleted.)

(vi) Number and location of all such components (includes other HLAP nuclearplants).

(vii)

Corrective action taken/to be taken, including responsibility for corrective action, schedule for corrective action or length of time taken to correct.

l l

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g., , .a a e 3

1. RCC. No Rtv No MOUSTCN LIGHTING & P2At2 COMPANY SOUTH TEMAS PROJtcT i Pmoctou;E MANUAL PLP-02 5 .

.aos o, b v.n PROJECT LICEN$1NG PROCEDURE 22 24 , i!

) i.

REPORTING DESIGN AND CONSTRUCTION 05-21-85  !

DEFICIENCIES TO NRC i

ATTACHMENT 9.7 Page 1 of 1 l I

PPOCEDURE FLOW CHART l

t origsretor s Engineertne  ;

Prepares f Nevie=5 Off OtF l

[

T Yet / $l gnif ttent\? h3 s Copy to l r Originator hetification by AC.

1 \ f a

Weae:r 5.op11ee. Com.

salta9t. Centractor IRC pevie. 1AC EI* l; 4 "*[Vertflet '

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At Leest IRC Chalmen Technical i PCtentially el4 hCitfien 4r v41det106 Reportatle haC (Prepared I

lac  :

ne.te. l I i bettfy Reportable heittei f

- Clone DAC I9: el) Re;cet to hAC i f

i I

I I

_ _ _ - _ - - _ ~ _ _ . = . . - . _ _ . _ = .- ~_ .

S'81,4 et 33

, . MUSTON Ll3HTIN3 & Powt:3COampANy scoc ho i SOUTH TEX AS PROJECT PROCEDURE MANUAL FLP-02 TsTLE

' ACE 08 PROJECT LICENSING PROCEDURE 23 REPORTING DESIGN AND CONSTRUCTION '" !'5 "

• DEFICIENCIES TO NRC 05-21-E :.

ATTACHMENT 9.8 List of Responsible Individuals Manager, STP Deputy Project Manager General Manager, Nuclear Engineering Manager, Engineering (STP)

Manager, Nuclear Purchasing Manager,QA Manager, Project 0A Manager, Nuclear Services Manager, Nuclear Fuel Manager, Nuclear Licensing Principal Engineer, STP Special Coordinator Supervising Project Engineer (Systems)

Supervising Project Engineer (Physical Design)

Supervising Engineer, STP Licensing Supervisor, Project Design / Procurement QA

!RC Chairman W2/F002/a

. . ste sea n su FOOC. NO - REV. NC

$80USTCN Lt2HTIN3 O PQ7.EQ CiMPANY SOUTH TEX As PROJECT PLP-02 5 PROCEDURE MANU AL PAGg op TITLE 24 24 PROJECT LICENSING PROCEDURE

)

'ssu s o

'" REPORTING DESIGN AND CONSTRUCTION 05-21-85 DEFICIENCIES TO NRC e

ATTACHMENT 9.9 Litting Of Those Individuals Responsible For The Architect-Engineer and/or NSSS Supplier Interface Manager, STP Deputy Project Manager Manager, Engineering Principal Engineer, STP SupervisingProjectEngineer(Systems)

Supervising Engineer, STP Licensing Supervisor, Project Design / Procurement QA 3

/

IRC Chairman Licensing Engineer, STP e

i i

I f

W2/F002/a

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