ML19309H784
| ML19309H784 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 03/19/1980 |
| From: | Jacobi L HOUSTON LIGHTING & POWER CO. |
| To: | |
| Shared Package | |
| ML19309H770 | List: |
| References | |
| PEP-11, NUDOCS 8005190714 | |
| Download: ML19309H784 (17) | |
Text
gnnest907l@
HOUSTON 1.tGHTING & POWER COMPANY L. R. Jacobi SOUTH TEXAS PROJECT PEP-11 1
P CEDURE MANUAL.
O Pr.oC. NO.
REV NO.
PAEPtRED BY TITLE PROJECT ENGINEERING PROCEDURE
)
37 susaecT REPORTING DESIGN AND CONSTRUCTION 3/19/80 DEFICIENCIES TO NRC oaTE issueo APPAOVED BY P
1 tiOUSTON LIGHTING & POWER COMPANY I hj
,,; V y
h SOUTH TEXAS PROJECT PROJECT ENGINEERING PROCEDURE PEP-ll REPORTING DESIGN AND CONSTRUCTION DEFICIENCIES TO NRC
.l. 0 PURPOSE The purpose of this procedure is to describe the South Texas Project program for complying with the requirements of both 10 CFR 21 and 10 CFR 50.55(e).
2.0 SCOPE This procedure establishes the requirements for review-ing, evaluating and reporting defects, non-compliances and deficiencies which could potentially affect the safety functions of the South Texas Project as defined by 10 CFR 21 or 10 CFR 50.55(e).
3.0 REFERENCE DOCUMENTS 10 CFR 21 10 CFR 50.55(e) 4.0 RESPONSIBILITY
/
4.1 Site Quality Assurance Supervisor The Site Quality Assurance Supervisor is responsible for performing a preliminary analysis of an incident to determine if it is possibly reportable.
The Site QA Supervisor is responsible for providing preliminary notice to the Resident Reactor Inspector of each possibly reportable deficiency.
4.2 Project Quality Assurance Supervisor The Project QA Supervisor is responsible for per-forming a preliminary analysis of an incident to determine if further analysis of the incident is required by the Incident Review Coimittee.
HOUSTON UGHTING & POWER COMPANY SOUTH TEXAS PROJECT PEP-11 PROCEDURE MANUAL paOc NO REV.NO.
I TITLE PROJECT ENGINEERING PROCEDURE 2
17
,,G, 0,
REPORTING DESIGN AND CONSTRUCTION DEFICIENCIES TO NRC O ATE ISSU EO 3/19/80 The Project QA Supervisor is responsible for notifying the Manager, South Texas Project and the Nuclear Regulatory Comission of in-cidents determined to be reportable pursuant f
to 10 CFR 21 or 10 CFR 50.55(e).
~.....es The Project QA Supervisor or his designee is responsible for preparing the minutes of all Incident Review Comittee meetings.
4.3 Manager, South Texas Project The Manager, South Texas Project is responsible for notifying the Vice President - Construction and Technical Services, of all incidents deter-mined by the Incident Review Comittee to be reportable under 10 CFR 50.55(e) or 10 CFR 21.
4.4 Team Leader, Nuclear Safety and Licensing The Team leader, NS&L is responsible for chair-ing all Incident Raview Comittee meetings.
The Team Leader, NS3L is responsible for pre-paring and submitting all written correspondence to the Nuclear Regulatory Comission as required by 10 CFR 21 or 10 CFR 50.55(e).
The Team Leader, NS&L is responsible for main-taining a file of all incidents considered by the Incident Review Comittee.
4.5 Incident Review Comittee The Incident Review Comittee is responsible for determining reportability of deficiencies per 10 CFR 50.55(e) or defects and noncompliances per 10 CFR 21.
Houston Lighting & Power has the ultimate responsiblity for determing report-ability of deficiencies per 10 CFR 50.55(e).
)
i
HOUSTON LIGHTING & POWER COMP AC?V SOUTH TEXAS PROJECT PEP-ll PROCEDURE MANUAL pnoc No.
REV.Nb.
TITLE PROJECT ENGINEERING PROCEDURE pace 3 Op 17 wancr REPORTING DESIGN AND CONSTRUCTION DEFICIENCIES TO NRC oarsissueo 3/19/80 In order to improve the. processing of incident N(HL,,,~l.}N}5 ll if reviews, convening of a joint session of the F
B&R and the HL&P Incident Review Comittees is i
d recomended.
5.0 REQUIREMENTS 5.1 Initial Incident Notification Defects, noncompliances or deficiencies which could potentially affect the safety functions of the nuclear power plant can be identified by numerous individuals and from various pro-cedures or interfaces.
Regardless of the in-dividual, orpanization or means of identifying such incidents, it is imperative that either the Site Quality Assurance Manager or the Project QA Supervisor be notified imediately so he can review the NCR (or ADR, if appropriate) and ini-tiate the evaluation process of the possibly reportable defect, noncomformance or deficiency.
The Site QA Supervisor shall notify the Resident Reactor Inspector within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of receipt by the Site QA Supervisor of each incident considered to be possibly reportable.
5.2 Safety Evaluation Each incident identified as being reportable'to the NRC per 10 CFR 21 or 10 CFR 50.C5(e) will receive both a technical evaluation cnd a safety evaluation to determine whether the incident could, if uncorrected, create a substantial safe-ty hazard. Technical evaluations are perfonned by the cognizant engineering organization and safety evaluations are performed by the Incident Review Comittee.
I t
l
HOUSTON LIGHTING & POWER COMPANY SOUTH TEXAS PROJECT PEP-11 PROCEDURE MANU Al.
pace. No CEV.NO.I 1
TITLE PROJECT ENGINEERING PROCEDURE PAGE 4 OF l7 REPORTING DESIGN AND CONSTRUCTION 3/19/80 DEFICIENCIES TO NRC D ATE ISSUED For the purpose of init.ial reportability deter-mination, the safety evaluation may be waived when an extensive safety evaluation is considered nec-essary and the disposition of the incident will re-sult in the retention of the original design configu-h!
[l llf]jf p ration and safety criteria.
In such cases, the g, g'l4)VIILhp-qf f
incident shall be considered reportable.
The final
~ ~ ' " -
J report shall then consist of a technical evaluation.
A safety evaluation shall be performed in all cases where the original design configuration or safety criteria will not be retained.
5.3 Deficiency Determination The following factors shall be considered in evaluating an incident to determine if it is a deficiency reportable to the NRC under the pro-visions of 10 CFR 50.55(e).
1.
The deficiency shall be evaluated as sffecting or having the potential to affect the safety of operation of the plant at any time throughout its expected life.
This includes deficiencies which could affect the safety-related function of any structure, system or component for which credit is taken in the FSAP. in evaluating their capability to acconnodate the effects of and to compatible with environmental conditions asso-ciated with norinal operation, maintenance, testing and postulated accidents.
Careful consideration shall be given to the effects of the deficiency to assure that it does not indirectly affect the safety of operation of the plant.
2.
The deficiency shall be related to the design or construction phases.
This includes activities of the Nuclear Steam System Supplier, architect engineers, consultants, contractors, or suppliers.
3.
The deficiency shall fall within one of the following four categories:
(a)
A breakdown in the Quality Assurance Program related to any criterion in 10 CFR 50, Appendix B, applied to any design or con-struction activity affecting the safety to plant operation.
HOUSTON LIGHTING & POWEO COMPONY SOUT!i TEXAS PROJECT PEP-ll PROCEDURE MANUAL n ev. no.1 anoe no TlTLE PROJECT ENGINEERING PROCEDURE
,,c, 5
17 og suancT REPORTING DESIGN AND CONSTRUCTION DEFICIENCIES TO NRC DATe lssuso 3/19/80 (b) A deficiency in final design as approved and released for construction such that the design does not conply to the design criteria and bases stated in the FSAR or Construction Permit.
Final design denotes those drawings, specifications and other engineering documents that have been re-viewed, approved and released for fabrica-()khf ' t,7-f i' I' ' 7--
tion, installation or construction.
No J
deficiency exists if a design stated in j
1!J the FSAR is changed by approved procedures after receiving proper evaluation and review.
(c)
A deficiency in construction of or damage to a structure, stem or component which will e
(d)
A deviation from performance specifications defined in the functional testing require-ments which will require extensive evaluation, extensive redesign, or extensive repair to establish the adequacy of the structure, system or component.
4.
The significance of the deficiency should be evaluated relative to operational safety.
The significance of a deficiency is a subjective evaluation and as such the significance of a given deficiency may not be clear.
Therefore, if the significance of a deficiency is in doubt, it should be treated as reportable to the NRC.
5.4 Defect Determination The following factors shall be considered in evalua-ting an incident to determine if it is defect report-able to the NRC under the provisions of 10 CFR 21.
1.
The incident identified shall involve either the software or hardware requirements associated with a basic component.
A basic component is a Safety Class 1, 2, or 3 Seismic Category I structure, system, component or part thereof necessary to assure:
HOUSTON UGHTING A POWER COMPANY SOUTH TEXAS PROJECT PEP-ll I
PROCEDURE MANUAL PAOC NO REV.NO.
flTLE PROJECT ENGINEERING PROCEDURE 6
17
,,og op SUBJECT REPORTING DESIGN AND CONSTRUCTION DEFICIENCIES TO NRC oats issueo 3/19/80 (a) The integrity of the reactor coolant pres-sure boundary;-
(b) The capability to shutdown the reactor and maintain it in a safe condition; or, (c) The capability to prevent or mitigate the consequences of accidents which could re-sult in potential offsite exposures com-parable to those referred to in 10CFR100.ll.
2.
The basic component shall contain a defect which
,, g 1s defined by the following categories:
(a) A deviation in a basic component delivered to a purchaser or user where on the basis of an evaluation, the deviation could create a substantial safety hazard; or, (b) The installation, use or operation of a basic component containing a defect as de-fined in paragraph 2(a) above; or, (c) A deviation in a portion of the nuclear power plant subject to the construction per-mit requirements of 10 CFR 50 provided the deviation could, on the basis of an evalua-tion, creata a substantial safety hazard and the portion of the facility containing the deviation has been offered to the pur-chaser for acceptance; or, (d) A condition or circumstance involving a basic component that could contribute to the exceeding of a safety limit, as defined in the technical specifications of a license for operation issued pursuant to 10 CFR 50.
3.
The defective basic component should be evaluated to determine whether the defect could, if uncor-rected, create a substantial safety hazard.
4.
A comercial grade item is not part of a basic component until after dedication which occurs after receipt when that item is designated for use as a basic ccmponent.
HOUSTON LIGHTING & POWER COMPANY SOUTH TEXAS PROJECT PEP-ll PROCEDURE MA[UAL I
pnoe No.
REV.NO.
ilTLE I
PROJECT ENGINEERING PROCEDURE 7
,,cE er 17 ws;ect REPORTING OESIGN AND CONSTRUCTION der ENCIES TO NRC care issoso 3/19/80 5.5. Noncompliance Determination The following factors shall be considered in evaluating an incident to determine if it is a noncompliance reportable to the NRC under the provisions of 10 CFR 21.
1.
The incident identified shall involve either the software or hardware requirements associated with a basic component.
Pg" ~3 g' ~i l
' "l
'~ '"" " " "" """' '""" '' ' ' "" ""
the Atomic Energy Act of 1954, as amended, or any applicable rule, regulation, order or license of the NRC relating to substantial safety hazards.
This includes failure to comply with design criteria and bases stated in the FSAR or Construction Permit.
3.
The basic component containing the noncompliance shall be evaluated to determine whether the non-compliance could, if uncorrected, create a sub-stantial safety hazard.
5.6 Incident Notifications Six primary notifications occur during the process of reporting defects, noncompliances and deficiencies in accordance with 10 CFR 21 or 10 CFR 50.55(e).
These notifications are:
1.
The Site QA Supervisor notifying the Resident Reactor Inspector of an incident determined to be potentially reportable pursuant to 10 CFR 21 or 10 CFR 50.55(e).
2.
Any individual notifying the Project QA Supervisor of an expected incident requiring consideration pursuant to 10 CFR 50.55(e) or 10 CFR 21.
3.
The Project QA Supervisor notifying the Team i
Leader, Nuclear Safety & Licensing of an in-cident requiring evaluation by the Incident Review Committee.
HOUSTON LIGHTING & POWER COMPANY SOUTH TEX AS PROJECT PEP-ll PROCEDURE MANUAL REV.NO.l pc]oc NO.
TITLE PH0 JECT ENGINEERING PROCEDURE 8
U
,,cy og REPORTING DESIGN AND CONSTRUCTION DEFICIENCIES TO NRC DATE ISSUED 3/19/80 4.
The Project QA Supervisor notifying the NRC of an Incident cons.idered reportable pursuant to 10 CFR 21 or 10 CFR 50.55(e).
5.
The Team Leader, Nuclear Safety & Licensing notifying the cognizant engineering discipline and others required to call a meeting of the Incident Review Comittee.
A 6.
The Manager, South Texas Project notifying the
,L - :- M - u u 0
Vice President - Power Plant Construction and Technical Services of an incident detennined to be reportable or potentially reportable.
5.7 Written Incident Report A written report is required to be submitted to the NRC Director of Regional Office and the NRC Director, Office of Inspection and Enforcement, on each defect, noncompliance or deficiency reported to the NRC per 10 CFR 21 or 10 CFR 50.55(e).
An outline for these written reports is provided in Attachment PEP-ll-01 l
to this procedure.
If infonnation required for the written report is incomplete when the report is pre-pared, an interim re ort shall be prepared describing r
that information which is available and a schedule for completing the remaining infonnation.
5.8 Incident Review Committee The Incident Review Committee shall consist o'f the following members, or their designees, as a minimum:
1.
Engineering Team Leader, NS&L - Chairman 2.
Project QA Supervisor 3.
Supervising Project Engineer, Design 5.9 Deadline Requirements 1
The following deadlines shall be observed l
A.
The NRC shall be notified by telephone (1) Within 2 days pursuant to 10 CFR 21 (2) Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> pursuant to 10 CFR 50.55(e).
following. determination by the Site QA Supervisor that the incident is possibly reportable.
HOUSTON LIGHTING & POWER COMPANY SOUTH TEXAS PROJECT PEP-11 1
PROCEDURE CANU AL pmoc No REV.NO.
TITLE
]
PROJECT ENGINEERING PROCEDURE
,,c, 9 o, 17 REPORTING DESIGN AND CONSTRUCTION 3/19/80 DEFICIENCIES TO NRC oAre issuer, B.
The NRC shall be sent a written report:
1 (1) Within 5 days pursuant to 10 CFR 21 (2) Within 30 days pursuant to 10 CFR 50.55 (e).
following determination by the Incident Review Comittee that the incident is reportable.
C.
Brown & Root shall submit to HL&P'for review a draft written report:
i YU Pmt"=aJe I4)-
(1) Witain 2 days for Part 21 deficiencies (2)
Within 17 days for Part 50.55(e) deficiencies.
following determination by the Incident Review Comittee that the incident is reportable.
5.10 PROCUREMENT DOCUMENT NOTIFICATION Attachment PEP-ll-02 to this procedure provides a standard statement that must be included in all purchase orders and subcontracts for services and equipment defined as being a basic component.
It is the responsibility of the Purchasing Department to ensure this statement is included in all such purchase orders and subcontracts.
5.11 POSTING REQUIREMENTS Attachment PEP-ll-03 to this procedure provides a standard poster which must be displayed in conspic-uous locations at both the Houston home office'and the construction site.
It is the responsibility of the STP Quality Assurance Supervisor to ensure that adequate posters are displayed in appropriste lo-cations.
This poster identifies the individual to whom initial notification of a defect or non-compliance should be made.
HOUSTON LIGHTING A POWER COMPANY
~
SOUTH TEXAS PROJECT PEP-ll
'l PROCEDURE MANUAL p=Oc. NO R EV. NO.
TITLE PROJECT ENGINEERING PROCEDURE
, ace 10 Or 17 REPORTING DESIGN AND CONSTRUCTION DEFICIENCIES TO NRC oaTe essueo 3/19/80 5.12 Proce'ure d
For a general flow charti of the incident review pro-cedure, see attachnent PEP-ll-04.
Responsibility Action Any Individual 1.
Reports to the Site QA Supervisor any inci-dent which he feels should be evaluated PRFilM!N:.ARY P#rsee#t to io era 50.55(e) or 10 CFR 21.
Site Quality 1.
Reviews the incident Assurance Supervisor report.
Site Qual.ity 2.
Determines whether it Assurance Supervisor is potentially report-a bl e.
Site Qual.ity 3.
If not potentially re-Assurance Supervisor portable, then handles incident through nor-mal QA channels Site Quality 4.
If potentially report-Assurance Supervisor able, then the Engi-neering Team Leader, Licensing is notified.
Engineering Team 5.
Reviews the incident Leader, Licensing report and discusses it with the Project QA Supervisor.
4 l
Engineering Team 6.
Arranges for review Leader, Licensing of the incident by the appropriate Engi-neering discipline.
Engineering Team 7.
Evaluates the safety Leader, Licensing significance of the incident.
HOUSTON LIGHTING & POWER COMPANY SOUTH TEXAS PROJECT pgp.11 l
PROCEDURE MANUAL p ;oc NO.
CEV.NO.
TITLE PROJECT ENGINEERING PROCEDURE pace 11 or 17 5"
REPORTING DESIGN AND CONSTRUCTION DEFICIENCIES TO NRC omre issuso 3/19/80 Engineering Team 8.
If not potentially re-Leader, Licensing portable, then incident is resolved through normal QA channels.
Engineering Team 9.
If potentially report-Leader, Licensing able then incident is referred to the Inci-dent Review Connittee.
L __ _....... :. 1...
Incident Review 10 Whenever possible, the Committee HL&P Incident Review Committee shall be con-vened as a joint meet-ing with the B&R Inci-dent Review Committee.
Incident Review
- 11. The Incident Review Commi ttee Committee considers the incident.
Incident Review 12.
If deemed not report-Committee able, then the incident is resolved through normal QA channels.
Incident Review 13.
If deemed reportable, Committee then the incident is reported to the NRC by the Project QA Super-visor.
Project QA Super-
- 14. Notifies NRC Region visor IV within the time frame noted in section 5.9.
Project QA Super-
- 15. Notifies the Manager, l
visor South Texas Project l
and the Manager, Qual-ity Assurance.
HOUSTON LIGHTING & POWER COMPANY SOUTH TEXAS PROJECT PEP-ll PROCEDURE MANUAL roc NO REV.NO.
TITLE PROJECT ENGINEERING PROCEDURE
,, G e 12 Or 17 SUBJECT REPORTING DESIGN AND CONSTRUCTION DEFICIENCIES TO NRC 3/19/80 OATeissueo Engineering Team Leader, 16.
Notifies the Super-Licensing vising Engineer, De-sign and the Super-vising Engineer Nuclear Safety & Licensing.
Engineering Team Leader, 17.
Prepares a written re-D@ gg. f. *w Licensing port to the NRC, Region IV within the time 2 6.
frame noted by section 5.9.
Engineering Team Leader, 18.
Prepares a documenta-Licensing tion package to be maintained by the Licensing group and RMS.
6.0 DOCUMENTATION Each defect, noncompliance or deficiency evaluated by the Incident Review Committee shall be recorded in formal meeting minutes by the Project Quality Assurance Supervisor.
A copy of these meeting min-utes, copies all telephone correspondence and copies of all NRC correspondence will be maintained by the Engineering Team Leader, Nuclear Safety & Li-censing; in cddition to the permanent record copy to be maintained by RMS.
It is the responsibility of each individual originating such documentation to en-sure that file copies are properly identified and transmitted to the Engineering Team Leader, NS&L and the Record Management System (RMS) File.
7.0 ATTACHMENTS A.
PEP-ll-01 " Incident Report Outline" B.
PEP-ll-02 " Procurement Document Statement" C.
PEP-ll-03 "Postihg Notification" D.
PEP-ll-04 " Incident Review Flow Chart"
woustoN ucwgNo a powen cow'rNv SOUTH TEXAS PROJECT PROCED!tRE CANUAL
,E bll nev.no. I T t T t.E oe uo PROJECT ENGINEERING PROCEDURE 5"C'
, ace 13 or 17 l
REPORTING DESIGN AND CONSTRUCTION DEFICIENCIES TO NRC oAre issuto 3/19/80 pgggggy ATTACHMENT PEP-11-01 INCIDENT REPORT OUTLINE I.
SUMMARY
This section should provide a synopsis of the incident and its resolution. The following information should be contained in this section:
a.
A synopsis of the incident b.
Postulated cause of incident A synopsis of the corrective action taken c.
d.
Synopsis of the results of the safety evaluation.
II.
DESCRIPTION OF INCIDENT This section should provide a clear and complete description of the incident and the circumstances surrounding it. The follow-ing information should be contained in the section:
Identification of the facility or activity or basic component a.
(including vendor) supplied to such facility or activity in-volved in the incident b.
Source and extent of incident The date and means by which the incident information was c.
obtained d.
Unusual circumstances pertaining to the incident, such as weather conditions, test procedures underway and/or abnormal conditions at site Status of construction at time of incident e.
f.
Procedures in effect to avoid incident (if any)
III.
CORRECTIVE ACTION This section should provide a clear description of the corrective action taken to rectify the incident and action taken to prevent recurrence. The following information should be contained in this section as applicable:
HOUSTON t.lGMTING & POWER COM7ANY SOUTH TEXAS PROJECT PROCEDURE MANUAL PEP-11 proc. iso.
REV.NO.
I TI T LL PROJECT ENGINEERING PROCEDURE l
- Act 14 OF l7
" ECT REPORT!NG DESIGN AND CONSTRUCTION DEFICIENCIES TO NRC oarsissuso _ 3/19/80 ATTACHMENT PEP 01 (cont.')
a.
The immediate response by Quality Assurance in response to the incident.
b.
A complete description of all ininediate actions taken to correct the incident.
c.
A complete description of all long-range actions to be taken to correct the incident and implementation schedule.
d.
A delineation of the testing methods which will be utilized to ensure that repairs have been conducted properly.
e.
Action taken to prevent the recurrence of the incident during the remaining construction phase of the facility.
IV.
SAFETY ANALYSIS This section shculd provide sufficient information to fully ana-lyze and evaluate all the possible safety implications of the incident. The following information should be contained in this section as applicable:
a.
Nature of the incident and the safety hazard which is created or could be created.
b.
Identification of applicable Quality Assurance documentation.
c.
A record on all incidents noted in the Quality Assurance documentation and their resolution where applicable to the reported incident.
d.
A complete record of the incident and the results of all investigations.
e.
Postulated cause of incident.
f.
A complete description of all inimR.te actions taken to mitigate the consequences of the incident.
g.
In the case of a basic component which contains a defect or noncomplaince originated for evaluation by B&R, the number and location of all such components in use at, supplied for, being supplied for other facilities or activities with B&R as the engineer or constructor.
HOJSTON t.1GHTING & DOWE R COMP AMV SOUTH TEXAS PROJECT PEP-ll PROCEDURE MANUAL ceoc wo.
nev. no.
1 T 6 Y L.E PROJECT ENGINEERING PRGOEDURE
, ace 15 0,
17 REPORTING DESIGN AND CONSTRUCTION DEFICIENCIES TO NRC
- omre issuro 3/19/80 6{
ATTACHMENT PEP-11-02 PROCUREMENT DOCUMENT STATEMENT 10 CFR 21
" Reporting of Defects and Noncompliances" The work to be performed under this purchase order (subcontract) is con-sidered to involve a " basic component" as defined by Title 10 Code of Federal Regulations Part 21 (published 6/6/77 in Federal Register).
Therefore,10 CFR 21 is applicable.
l 1
l l
myp ms1 A h gicmas 10 CFR Part 21 Reporting of Safety-Related Defects and Non-Compliances gaoc...
,,,.33 m. no.,
SS ED 3/19/80 The Nuclest Regula:ory Commission requires directors and responsible officers of certain firms and organizations to report defects in components and failures to comply with regulatory requerements that may result in a substantial safety hazard. The new regulations are identified as: Title to Chapter 1 Code of Federal Regulations - Energy - Part 21. They apply to firms that:
- Build, operate, or own NRC licensed facilities or conduct NRC. licensed or regulated activities.
- Supply safety.related components for NRC licensed f acilities.
- Supply safety.related design. testing. inspecting or consulting services for NRC licensed facilities.
Tne following documents provide information relative to the reporting of safety.related defects and non.
conformance.
A COPY OF 10 CFR PART 21 is LOCATED A COPY OF THE PROCEDURE FOR IMPLEMENTING 10 CFR PA81T 21 IS LOCATED ANY DEFECTS OR NONCOMPLIANCES WHICH COULD POTENT! ALLY AFFECT THE SAFETY FUNCTIONS OF THE NUCLEAR POWER PLANT SHOULD BE REPORTED TO P.rts of the f.d.r.I !.w.nd regul. tion concerning this r quit.m.n:
to r. port s.f.ty-r.l.t.d def. cts.nd non compli.nc..re.
PUBUC LAW 93 438 ENERGY REORGANLZATION ACT OF 1974
- s.c 206 a. Any memeu.s a.r.ei,,,,,
n
,g..,,,e.,,,..,,m 10 CFR PART 21 - JUNE 10.1977 con structmg. o*"me. co.r.une. or.uao yme tne comoon.nts of.ny PURPOSE e
f.clety or.cimey wne s,c.n d or ein.rwe r.gul.t.d pur.u.nt
- i. (n. Aiom.c En.re, Aci of 1954....m.rus.d. er pur.u.no ines Act. wno cet.m..nform.t n r.
n.tay en c.tmg m.:.uca f. carry
- 21.1 Purpo - Th. e. gut.t.orm.mit rt 64 n pron.our.s
.nd r.euw-n.nt. for.mpi. ment n W s.cwon 20s of m. En.rp or.ct
.r, or n..ic comoon.nt..upo d to. wen f.ciarry or.cimey -
s (1) F..i. i. o.mo., w.m tn. Atom.c En.rgy Act of R.org.n a.i on Act of 1974 Tn. ci n t.qu..s.n, enamou.f 8".ct.'.'
r".0".'#8. ## c-r of. Esm o.n.tructmg. c,wnee
--.a. -.uwvm m. '
e.nr i.ca
-.eimi, 1954.
.m.no.d. or.n,. gor.c.M. rui.. r.gul.i.on..re.r..r j
% e = com m..
nre.un.
.u
. ~ i w,no
.e. i.e.a
- e--
ii
-.=. m. A-.c m con..n...r.ci.n. o. - c,
...u ni.
so.r Aci, i ss4...~n=<.= cn-c n
.n aci e a
wm no.r. w.n = r a
.,n.cn m.c n.n.,
= i.u.
.n. me--.
n,
n,.n.c..,,,
- -uw=.us..
m ic,
,m.c.,n.n n,
5
..-*,.-*.uca ci.ni
. nn.
S
.u
.uc=av.w i = e
, - no.e n.~
= c in in,comm nn n
,m.,,,
ca,,
a.
n, in in. 4..m.e
$ en.ra cie ies4..
n r
n.
- u..e a
i e w.ci-e.a,.
m an,-
an n
.n..on.c u.
3 -e.- - e m.c
-,...un num - m w n
- m. noi - r.eu w % m,
ct
.n
=nr-t co.. - a nce,.n.n.m.u
.ew. m.
n ni m w. m.
e -~
w
.nzu,m.4 en.,,,
,i u...,,,
w..uca e.a, -
- n. w.c
.,,,e m m,.eu. - < m.
n,,
no.. w = n e. nm
.i,n.*
m.
nn*,,o
.nm.-n
.n,
,,n c
. n s-e.a-.
,, i.
w.ct. -a
- n. no r.eul.t.s pur.u.ni i. m. Aa.mic En.,y,4e et 1es4..e om w.e
.eru.s krww6 o. in in. e _ _-
n m n eu.i..,
.nsrm. e
-e.A,..
sowc=
- ..uin.n u.,
=
in
.ne r
ni i
nw.-
=,
. n.
.'D
- D-D T
E 1
_b, _ _
oe 6
Houston UGHTING & POWER COMPANY SOUTH TEX AS PROJECT PEP-ll CeV NO. q
- ROCEDURE MANUAL pooe No TI T LE PROJECT ENGINEERING PROCEDURE 17 17 PAGE OF S W ECT REPORTING DESIGN AND CONSTRUCTION 3/19/80 DEFICIENCIES TO NRC e4Teissuso Y,
INCIDENT REVIEW FLOW CHART ATTACHMENT PEP 1144 P
a e
..o...
..s-E R TO (NVIRONasENTAL A/E GA MONE OFFICE?
(GUF.MirPUEst t
t t
t ORMANCER N T (NVIRONMENTAL A/t GA PREPARE 0 hCR PREPARio BY Snt QA PROL Surt RV50R t
MO RE INF9. 5UPPLED BY QA SUPE RVl108 SITE 0A GR ENGINEERING f
Jl
= OA NO UNDETE RasiNE C
)
WNETHE R DEFECT, DEFICIENCY OR ONCONFORMANC N RC INFORM ALLY YES NOTIFIE 0 ly l
lC UR CE NCREEN TOSTP ggg I'
10 CPR 21 1I to CF A H.51 lei OtFICIENCY CONTKNow NO INVOLVE 3 A DON'T KNow NO M
ADVERSELY AFFECTS sAsaC CoasPONENT?
SAFETY?
6 (A) ygg VfS INC10E NT 13 NOT REPORTA$LE DEFIC!ENCY CD Ma EE CON t1RS
- INCIDENT YES REPORTA8LE?
QA YES m
k le CF R 2121 W (21 f
uGR.m MOTIFIES ENG R. TEAM LI ADt R. LICIN58NG PROJ. QA SUP NOTIFIES.
Vf. CON 57.4 TECM-NOTIFIES tTP E NGINE E RING MGR.$TP MGR OF QA, All QA SE RVICES SUPfa68.Ntat PROJ QA SUP NOTIFIES WRC REGlos iv it CFR 21 k 10 CF A SS.M let it CFR 21 Y 10 CF A 50.M lel I
I I
I N
INTERIM REPORT INTE RIII REPORT IW50AYS IN M DAYS te CTR F1 ft CFR 50.55 W ftL[PNON(
I FINAL REPORT FINAL REPORT FINAL REPORT
(
INNUTES PREPAREO IN 5 0Ays IN 30 0 AYS I
1r
~
RESOLVI BY FINAL REPORT suessTTto OClou
-