ML17194A072
| ML17194A072 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Byron, Braidwood, Quad Cities, Zion, LaSalle  |
| Issue date: | 08/07/1981 |
| From: | Swartz E COMMONWEALTH EDISON CO. |
| To: | Haass W Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17194A073 | List: |
| References | |
| 4031A, NUDOCS 8108140128 | |
| Download: ML17194A072 (3) | |
Text
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CommonwAi Edison 72 West Adam;Ye'~t. Chicago, Illinois Address Reply to: Post Office Box 767 Chicago, Illinois 60690 Aug.us t 7, 1981 Mr. ~e Pe Eaess, Chitf Qu.;;lity Assurance branc.l; -
l*r:t:
U. S. 1uclear Rcgul~tcry Cct~iEsicn
~asbin~ton, L. c.
2C555 S~Lject: COrrDonweelth E~isc~ Co~pany
~uslity As~urence Frcgre~
1cric~l Rcpo~t CE-1-A [Evieions N[C Lkts. 50-lC, 50-237, 50-245, 50-254, 50-2C5, 50-295, 50-30~,
50-373, 50-374, 50-454, 50-455, 50-~56 ecd sc-r57
/,ttacbcc'. c:rc th: fcllo~;ir.[ liEtcG rcvi:::£.c~ pc:zcr. CEte.d f:,/7/£1, Rev. 1£:, tc tl..c sL1.Ljcct ~crie:c::l Bcpcrt cicscril:..ir:[ ttc Cor.:!:.ionwee l th Edi sen ~ual i ty As1rnrancc Fro gr aw.
Pages:
2-2 and 2-6 1'h i c r c vi r. ion i ci ~ r; t i f i e s tr e Re r, t.: 1 at cry Gu i de r and Ar SI Stsnd~r~s that apply tc cur respective nuclear st~ticnE. 1hosc listt:*d as rpplic'-tlc tc I>rcs(c::r., (uad Citie,:-:: and Zior: rt*clcc:r Fower Stations generally arc these which were covered by our coc.rdtr;:cnt to the "P..:into\\*: r.oc!cc" enc fer la~.:-lle, Byrer. end Ereic.i-
~ood those i~entificd in the respective FSAR's.
Also, this rEvisior applies the Quality Assurence Program to the reviEw of ecvironmc&ttl quclif icction of Class lE I:quipmcr.t.
Very
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Guides and the requirements of the following ANSI Standards as listed for each station
- I.
Dresden, Quad Cities and Zion Nuclear Power Stations 1.28 (Safety Guide 28 - 6/72); 1.30 (Safety Guide 30 -
8/72); 1.33 (Safety Guide 33 - 11/72); 1.37 - 3/73; 1.38 - 3/73; 1.39 - 3/73; 1.54 - 6/73; 1.58 - Rev. l; 1.64 - 16/73; 1.74 - 2/74; 1.8 (Safety Guide 8 - 3/71);
1.146 - Rev. 0 8/80; ANSI N45.2.8-74 (Draft 3, Rev. 3, 4/74); ANSI N45.2.5-73 (Draft 3, Rev. l, 1/74); ANSI N45.2.9-74 (Draft 15, Rev. 0, 4/74); ANSI N45.2.12-74 (Draft 3, Rev. 4 2/74); ANSI N45.2.13-74 (Draft 2, Rev.
4, 4/74)
II.
LaSalle County Nuclear Power Station 1.28 - Rev. 0, 6/72; 1.30 - Rev. 0, 8/72; 1.33 - Rev. 2; 1.37 - Rev. 0, 3/73; 1.38 - Rev. 2; 1.39 - Rev. 2; 1.54 - 6/73; 1.58 - Rev. l; 1.64 - Rev. 2; 1.74 - Rev.
0, 2/74; 1.8 - Rev. 1-R; 1.88 - Rev. 2; 1.94 - Rev. l; 1.116 - Rev. 0-R, 6/76; 1.123 - Rev.* l; 1.146 - Rev. 0, 8/80 III.
Byron and Braidwood Nuclear Power Stations 1.28 - Rev.l; 1.30 - Rev. 0, 8/72; 1.33 - Rev. 2; 1.37 -
Rev. 0, 3/73; 1.38 - Rev. 2; 1.39 - Rev. 2; 1.54 - G/13; 1.58 - Rev. l; 1.64 - Rev. 2; 1.74 - Rev. 0, 2/74; 1.8 -
Rev. 1-R; 1.88 - Rev. 2; 1.94 - Rev. l; 1.116 R, I
6/76; 1.123 - Rev. l; 1.146 Rev. 0, 8/80 Exceptions or alternatives to this _Topical Report for specific plants identified in the Safety Analysis Report or Technical
- Specification will take precedence over commitments in this Topical Report.
It is also the policy of Commonwealth Edison Company to assure a high degree of functional integrity for its gene-rating facilities so as to achieve high availability of these facilities for the production of electrical power and to main-tain overall quality levels which will.achieve the foregoing in a safe, effective and economic manner.
The Quality Requirements and Quality Procedures of the Company Quality Assurance Program Manual (see Appendix A for Program Manual Index) ~s described herein, document the 2-2 Rev. 19 19 8/6/81 Commonwealth Edisor
The training and certification of personnel associated
. wi~h nondestructive examination will be carried out in accord-ance with the requirements of SNT-TC-lA and the Code.
A Level III certified person will administer this activity and the program will be under the surveillance of the Directors of Quality Assurance or their delegated representatives.
Like-wise, a Level III certified person will administer the concrete containment inspection as applicable under Division 2 of the ASME Code.
Training and certification of personnel associated with concrete containment inspection will be carried out in accordance with Appendix VII of ASME Section III, Division 2.
The period of qualification shall be a minimum of two and a maximum of three years.
Near the end of such a period, employes will be notified that they will require either retraining and requalification and/or recertification to renew their qualification status.
Contractor personnel engaged in inspection, examina-tion and testing activities will be required to be trainined, qualified and certified to perform their specific activity in accordance with the above requirements.
Such training will be documented and the record of those receiving training shall include as a minimum the dat~,
subject and the name of the person who performed the training.
The objectives of the Commonwealth Edison Company Quality Assurance Program are to:
(1) establish with confidence that the design, fabrication, erection and operation phases of *its nuclear power generation facilities are performed in a manner consistent with the policies stated above; (2) provide for documenting, retaining documentation and updating design, fabrication, erection and product quality information necessary for Commonwealth Edison Company opera-tion, maintenance, repair, modification, refueling and in-service inspection of the nuclear power facilities; (3) avoid schedule delays and high cost due to poor quality; and (4) achieve high plant reliability and availability.
The Quality Assurance Program applies to safety-related and AS~lE Section III activities and items and related consumables plus fire protection, security, emergency plan, meterorology, radwaste shipment and review of environmental qualification of Class lE Equipment.
The classification of 19 structures, systems and components designated as "safety-reLited" are listed in the respective Safety Analysis Reports (SAR) of the Stations.
A copy of the SAR or the listing will 2-6 Rev. 19 8/6/81 Commonwealth Edison