ML20214U124
| ML20214U124 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/01/1986 |
| From: | Anderson F, Mcnult G TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20214G966 | List:
|
| References | |
| 209.1(B), 209.1(B)-R, 209.1(B)-R00, NUDOCS 8612090147 | |
| Download: ML20214U124 (16) | |
Text
_ _ _ _ _ _
j TVA EMPLOYEE CONCERNS REPORT NUMBER: 209.1(B)
SPECIAL PROGRAM (I'
REPORT TYPE:
SEQUOYAH ELEMENT REVISION NUMBER: 0 TITLE:
Q-LIST Q-List Differences PAGE 1 0F 15 REASON FOR REVISION:
a PREPARATION 1
PREPARED Y:
bt 0 (iflh SIGNATURE DATE REVIEWS lO "Eo ~&
SIGNATURt
/
DATE TAS:
SIGNATURE DATE CONCURRENCES 8612090147 861124
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PDR ADOCK 05000327 lOY //-/-fC CEG-H:
yf V
SRP:
SIGNATURE DATE SIGNATURE DATE e
APPROVED BY:
ECSP MANAGER DATE MANAGER OF NUCLEAR POWER DATE CONCURRENCE (FINAL REPORT ONLY)
TVA EMPLOYEE' CONCERNS REPORT NUMBER:
209.l(B)~
SPECIAL PROGRAM REVISION NUISER: 0 PAGE 2 0F 15 1.
CHARACTERIZATION OF ISSUE (S):
Concern:
Issues:
IN-85-407-001
- a. The documents (Q-Lists or equivalent)
"CSSC Q-List is not-accurate.
used on SQN to identify the applic-Not all components covered by ability of QA program controls are not QA program are listed. QE accurate and complete.
Department has list that docu-ments the inaccuracies. The
- b. The use of inadequate Q-Lists (or' equi-CSSC Q-List is used to determine valents) on SQN could have adversely if QC inspections are required.
affected the establishment of appro-CI has no further information."
priate quality control on items that are related to plant safety. By IN-85-688-003 reference to an inadequate Q-List, the
" Concern over validity of Critical possibility exists that "Non-Q" items System, Structures and Components are installed in a safety-related
'Q' listing. Details known to system.
(This issue is addressed in QTC. Details withheld to main-Element Report 209.2, not in this tain CI confidentiality."
report.)
.a 98
- c. Various Q-Lists (or equivalents) exist IN-86-087-004 on SQN, which are different in content.
"Significant differences exist in the content of the Nuclear
- d. The engineering design group does not Power 'Q' List and the Critical provide input to the Q-Lists (or Structures, Systems and'Compo-equivalents) on SQN.
ments (CSSC)
'Q' List. Many items originally placed on the NUC Power 'Q' List are not reflected on the CSSC
'Q' List, which could adversely affect establishment of appropriate quality controls on items which are related to plant safety.
Nuclear Power concern. No l
specifics provided. CI has no further information."
4 IN-86-090-001 "NUC PWR (No name/ dept. given) l issued a Critical Structures,
(
Systems and Components List (CSSC) that does not include all
)
0929d (10/16/86)
TVA EMPLOYEE CONCERNS REPORT NUM8ER:
209.l(B)
SPECIAL PROGRAM e
REVISION NUMBER: 0 g.
PAGE 3 0F 15 items identified on the site
'Q' List (No specifics given).
This was done without Office of ENG, ENG Design Group input /
approval (The originator of the site 'Q' List). By referring to i
the CSSC, the possibility exists for installing 'Non-Q' items in a Safety-Related System. CI has no additional information.
NUC POWER concern."
2.
HAVE ISSUES BEEN IDENTIFIED IN ANOTHER SYSTEMATIC ANALYSIS? YES X NO l
Identified by TVA SON Generic Task Force (6 CTG)
Date June 2. 1986
{
Documentation Identifiers:
GOR-16-16, Rev.1
- yh F.4 Report 60R-16-16, Rev. I documents results of an investigation for l
SQN of Concern Number IN-85-688-003.
3.
DOCUMENT N05.. TAG NOS.. LOCATIONS. OR OTHER SPECIFIC DESCRIPTIVE j
IDENTIFICATIONS STATED IN ELEMENT.
I None 4.
INTERVIEW FILES REVIEWED:
1 a.
Expurgated QTC File for IN-85-688-003. This file contained a j
copy of the Employee Concern "K" for.n, and a brief expurgated I
interview statement with no additional information.
l b.
Expurgated QTC File for IN-86-090-001. This file contained a copy of the Employee Concern "K" form, and copies of I
documents previously reviewed by this evaluator.
c.
Expurgated QTC File for IN-85-407-001. This file contained copies of the Employee Concern "K" form, ECTG Administrative i
forms, and documents previously reviewed by this evaluator.
d.
Expurgated QTC File for IN-86-087-004. This file contained copies of the Employee Concern "K" form, ECTG administrative forms, and documents previously reviewed by this evaluator.
0929d (10/16/86)
TVA EMPLOYEE CONCERNS REPORT NUMBER:
209.1(B)
SPECIAL PROGRAM REVISION NUMBER: 0 PAGE 4 0F 15 5.
DOCUMENTS REVIEWED RELATED TO THE ELEMENT:
See Appendix A.
6.
WHAT REGULATIONS, LICENSING COMITMENTS, DESIGN REQUIREENTS, OR OTHER APPLY OR CONTROL IN THIS AREA?
See Appendix A.
7.
LIST REQUESTS FOR INFORMATION, MEETINGS, TELEPHONE CALLS, AND OTHER DISCUSSIUus) RELAltu 10 ELtritRI.
See Appendix A.
8.
EVALUATION PROCESS:
W.
a.
Determine the use of Q-Lists (or equivalent)
W on SQN as the method for identifying which items require QA program controls, b.
Review the procedures and practices governing the methods determined in "a."
c.
Review the implementation of procedures and practices in "b."
d.
Evaluate the adequacy of this information to resolve the issues associated with this element.
9.
DISCUSSION, FINDINGS, AND CONCLUSIONS:
Discussion:
a.
The four employee K-forms associated with element 209.1 document general concerns about the existence of different Q-Lists on Watts Bar Nuclear Plant (WBNP), the accuracy of the lists, and the impact of using those lists. Although these concerns resulted from specific applications and conditions at WBNP, they have been classified as generically 0929d (10/16/86)
TVA EMPLOYEE CONCERNS REPORT NUMBER:
209. l(B)
SPECIAL PROGRAM REVISION NUMBER: 0 PAGE 5 0F 15 applicable to the other TVA nuclear plants, including Sequoyah, because the potential exists for similar deficiencies in the related lists of the other facilities.
b.
"Q-List" is a generic term used by the nuclear power industry to describe a listing of the plant structures, systems, and components that are to be covered by, the Quality Assurance (QA) program requirements of 10CFR50 Appendix B.
There is wide variation in the format and detail of the Q-Lists in existence within the nuclear power industry, from summary type lists containing only first-level identification, to extensive listings with subcomponent identification and detailed data.
The listing for Sequoyah is identified as the Critical Structure, Systems, and Components (CSSC) List, and is of the summary type. The SQN CSSC List is characterized as a working document, with everyday usage in Sequoyah activities including modifications, maintenance, and procurement.
However, the use of the SQN CSSC List is limited to only the O
Operations organization; the list was not used by 9/
Construction or Engineering on SQN.
The individual system drawings (P& ids, flow diagrams, etc.)
developed by Engineering identified the safety-related structures, systems, and components on SQN. These drawings were the source documents, rather than the SQN CSSC List, used by the Construction organization to detennine the items that required QA program controls.
Construction Specification N2G-877 was issued to provide guidance for Construction in identifying items requiring QA program controls. Tables were included as part of N2G-877 (prior to revision 5) which contained generalized convenience listings of safety-related items. However, the tables were used only as guidelines and do not constitute a "Q-List."
The current revision of N2G-877 (Rev. 5) allows Construction to use a "Q-List" (91QL series drawings) as an alternate to the system drawings for identification of items requiring QA program controls. However, the 31QL' series drawings have not been implemented on SQN, pending the Q-List development activity outlined in 9.c.
c.
Q-List development and implementation on the TVA nuclear plants are undergoing examination and change within TVA at present. TVA policy documents, including the Nuclear Quality Assurance Manual (NQAM), have established the commitment that 0929d (10/16/86)
TVA EMPLOYEE CONCERNS REPORT NUMBER:
209.l(B)
SPECIAL PROGRAM REVISION NUMBER: 0
[
PAGE 6 0F 15 the Division of Nuclear Engineering (DNE) will develop and maintain a Q-List for each nuclear plant. The DNE-developed Q-List will be used by all divisions within a plant to maintain uniformity.
As the lead plant for implementation of the DNE-developed Q-List, WBNP initiated replacement of the CSSC List by the Q-List.
Inaccuracies and problems subsequently identified in the WBNP Q-List were documented in NCR W-269 and reported to the NRC as a 10CFR50.55(e) "significant deficiency" for WBNP. Corrective actions for that condition are still in progress within TVA, and have impacted the development of a uniform Q-List approach for TVA. The employee concerns associated tf th this element directly involved the problems i
associated with the WBNP Q-List.
The timing for implementation of a DNE-developed Q-List has become a plant-unique situation, with the NQAM prescribing that the SQN Q-List will be put into effect, "... at a date mutually agreed to by DNE and the NSD" (Nuclear Site D_'
Director).
In the meantime, the SQN CSSC List continues in use at SQN.
d.
The SQN CSSC List was developed and used by the Nuclear Power (NUC PR) organization for application to the Operational QA Program. The list has successively been a part of the Operations Quality Assurance Manual and the NQAM, and is now contained in Sequoyah Standard Practice SQA-124. Since the SQN Q-List was developed, responsibility for it has passed from NUC PR to the QA Organization to the NSD at present.
Control of the SQN CSSC List is established through Sequoyah Administrative Instruction AI-39, which provides for a SQN CSSC Review Committee to maintain the SQN CSSC List. AI-39 cites the following pertinent requirements and responsibilities for the SQN CSSC Review Committee:
o Membership consists of a designated representative from each of the following groups:
Engineering Group - Chairman Administrative Services - Secretary Regulatory Engineering Quality Assurance Maintenance (Instrument, Electrical, Mechanical)
Design Services f
i 0929d (10/16/86) 4
6 TVA EMPLOYEE CONCERNS REPORT NUMBER:
209.l(B)
SPECIAL PROGRAM REVISION NUMBER: 0 PAGE 7 0F 15 l
(Note: The evaluator was informed that committee membership requirements are being changed to reflect the l
present TVA organization. _The " Engineering" representatives indicated above from the currnt revision of AI-39, are not DNE personnel, but are from the Operations organization..)
4 o
The committee is required to meet at least once per l
quarter, and has had six formal meetings in the last 15 l
months.
o Meeting results are documented, and recommended changes i
to the CSSC List are submitted for Plant Operations Review Committee (PORC) review and Plant Manager's approval o
The committee is required to perform a biennial review of the CSSC List to ensure that the list is accurate and complete d
e.
The review of reference documents identified various cases of l'*
direct or inferred concern regarding the accuracy and completeness of the CSSC List, including the following:
o ANI Inspection of SQN dated September 10-13, 1984, (App. A, 5.r) recommended, "The safety-related equipment i
list should be reviewed periodically for completeness 1
and accuracy by the cognizant group. Additionally,' the Office of Quality Assurance (QA) should ensure an adequate review through the audit process."
o' The Of fice of Engineering, Design, Construction document, OEDC-2QPD-5, (App. A, 5.1), established the commitment for Engineering to prepare a Q-List for each i
a nuclear plant, and includes the statement, "... The Sequoyah list is not current or specific...." This apparently refers to the SQN CSSC List in place at that time (1982).
o SQN CSSC Review Committee Meeting' Minutes (App. A, 5.u) contain agenda items that imply that the completeness o
l and accuracy of the existing CSSC List is indeterminate, for example:
" Determine accuracy of SQN CSSC List for instruments and controls and revise the CSSC List as
}
required."
{C,,
- O ii j
0929d (10/16/86) h
TVA EMPLOYEE CONCERNS REPORT NUMBER:
209.l(B)
SPECIAL PROGRAM REVISION NUMER: 0 PAGE 8 0F 15 o
SQN Generic Concern Task Force Report GOR 16-16 ( App. A, 5.n) contains recomendations which include:
"A timely review for completeness and accuracy should be conducted to ensure the adequacy of the 'CSSC' List as comitted to in the response to ANI, dated December 19, 1984, letter (L64 850104 303)."
The review of case file documents did not indicate that a review of the SQN CSSC List had been accomplished to date.
Minutes of the CSSC Review Comittee meetings reflected that the comittee performed numerous activities responding to
" Request for Revision to CSSC List" forms, but those activities do not constitute a complete review of the SQN CSSC List.
f.
There are indications (listed below) that action items associated with the SQN CSSC List are being deferred to the pending DNE Q-List development.
o The TVA comitment to review the SQN CSSC List for
[',,;
accuracy and completeness on a biennial basis appears to C
the evaluator to be an action drifting towards deferral to the pending Q-List cogletion.
o The CSSC Review Comittee has deferred the determination of proper CSSC classification of numerous items to the pending Q-List completion.
ID-QAP-2.7, governing the development, control, and application of a Q-List for each nuclear plant has undergone several revisions extending the implementation comitment for the SQN Q-List.
It now states that the SQN Q-List will be put into effect at a date mutually agreed to by DNE and the NSD. However, the development and implementation of the SQN Q-List will apparently not occur until af ter completion of the upgrade and revision activities currently in process for the WBN Q-List.
The pattern of deferring the resolution of various CSSC List items to an indeterminate date in the future (associated with completion of the Q-List and its implementation on SQN),
results in a status quo situation for the CSSC List, g.
One of the four employee concerns in Element 209.1, IN-85-688-003, was investigated by the TVA SQN Generic Concern Task Force (GCTF). The results of that investigation are documented in GCTF Report G0R 16-16 (App. A, 5.n), which states that the scope of that investigation was "To determine if the CSSC List used for Sequoyah is accurate."
0929d(10/16/86)
TVA EMPLOYEE CONCERNS REPORT NUfEER:
209.l(8)
SPECIAL PROGRAM REVISION NUPBER: 0
^
PAGE 9 0F 15 The evaluator considers that the conclusions and recommendations stated in GCTF Report GOR 16-16 are contradictory and inconclusive, in that Section IV A.1 states as a conclusion:
"The issue was detennined not to be valid by this investigation because Sequoyah is using an accurate
'CSSC List' developed by Quality Assurance and not the
'Q-List' developed by the Office of Engineering."
While Section IV B.1 states as a recomendation:
"A timely review for completeness and accuracy should be conducted to ensure the adequacy of the 'CSSC' List as committed to in the response to ANI, dated December 19, 1984 letter (L64 850104 303)."
h.
NRC Report 50-327/86-11 ( App. A, 5.s) documents NRC inspection activities associated with followup of TVA's response to NRC Generic Letter 83-28 (App. A, 5.q).
Sections
- tM 2.1 and 2.2 of GL83-28 contain requirements for licensees to
- 6, confirm the safety-related identification of components of the reactor trip system, and to describe their program for ensuring that all components of other safety-related systems are identified as safety-related. Since TVA's response to this requirement referred to the SQN CSSC List as the program for equipment classification, the NRC inspection included the review of procedures and work documents associated with the CSSC List.
Results of the NRC inspection identified that the current program for maintenance of the CSSC List deviates from the program described by TVA in the initial response to GL83-28.
The NRC inspector also concluded that TVA's methods for revising the CSSC List lacked a formalized system for tracking CSSC Review Comittee ager.da items, and for requesting changes to the CSSC List. TVA's response (App. A, S.t) to the NRC Inspection did not address either of these items.
The NRC inspection also included a limited review (sample of
- 7) of Maintenance Requests to verify that work activities were being properly classified as CSSC or non-CSSC.
In the area of equipment classification, the NRC determined that there were no violations or deviations.
((:,
0929d(10/16/86)
TVA EMPLOYEE CONCERNS
-REPORT NUMBER:
209.l(B)
SPECIAL PROGRAM REVISION NtMIER: 0
,: 1 PAGE 10 0F 15 9
Findings:
a.
The SQN CSSC List is the "Q-List" type document in use on SQN to 3
identify items that require QA program controls. Although a review 1
of the SQN CSSC List for accuracy and completeness has been s
committed to by TVA, such a review has not been performed to date.
I 3
The activities of the SQN CSSC Review Comittee, while a positive f'
factor towards maintaining the SQN CSSC List as an "living" document, are not sufficient to establish the accuracy and completeness of the list. The following shortcomings are evident in the Review Comittee actions:
Il o
A TVA review of the SQN CSSC List for accuracy and i
completeness has not been accomplished to date.
Therefore the baseline, to which the CSSC Review Comittee is providing
};
l updates for plant modifications etc., is of undetermined
{
accuracy and completeness.
o The practice of deferring numerous classification actions to
,se -
the pending DNE Q-List development, contributes to the Ti Wid questionable status of SQN CSSC Lists accuracy and
}
completeness.
b.
The investigation indicated that only a single listing, the SQN 3
CSSC List, was used on Sequoyah. The Engineering organization had developed a " trial use" SQN Q-List, but it was not implemented on the project. Thus, the problems associated with the existence of several Q-Lists having different content were not applicable to Sequoyah.
)
Further, the TVA commitment to implement the forthcoming s
DNE-developed and maintained Q-List will adhere to the principle that a single list prescribing QA program applicability will be in 1
existence for SQN. Thus, at some future date, the SQN CSSC List will apparently be superseded by an SQN Q-List.
c.
The SQN CSSC List was initially developed and issued by NUC PR, and is presently the responsibility of the NSD through the Operations organization.
The CSSC List is maintained by the SQN CSSC Review Committee, which membership lacks direct DNE participation.
(
0929d (10/16/86)
TVA EMPLOYEE CONCERNS REPORT NUMBER:
209.l(B)
SPECIAL PROGRAM REVISION NUM8ER: O PAGE 110F 15 Review of CSSC Review Committee minutes indicates that specific items are referred to DNE for input, but that DNE involvement is only peripheral.
However, there is an indication that the SQN CSSC Review Committee composition is in the process of being modified to include a DNE representative.
The apparent absence to date of active DNE involvement with the SQN CSSC List is considered by the evaluator to be a shortcoming that diminishes the confidence level of the accuracy and completeness of the CSSC List.
==
Conclusions:==
The emoloyee concerns relating to the accuracy and completeness of the SQN CSSC List, and also those relating to Engineering design group input to the list, are considered by the evaluator to be valid concerns for SQN.
The concerns relating to the existence of multiple Q-Lists containing dif ferent content are not valid for SQN.
(i$
A TVA review of the SQN CSSC List is necessary to confirm its Q;"7 completeness and accuracy. The review should be performed with input from DNE to determine the degree of completeness appropriate for the list, and should include resolution of those action items previously deferred by the SQN CSSC List Review Committee.
l 0929d (10/16/86)
TVA EMPLOYEE CONCERNS REPORT NUMBER:
209.1(8)
SPECIAL PROGRAM REVISION NUM8ER: 0 PAGE 12 0F 15 APPENDIX A 5.
DOCUMENTS REVIEWE0 RELATED TO THE ELEMENT:
4 a.
10CFR Part 50, Appendix 8, Quality Assurance Criteria for 4
Nuclear Power Plants and Fuel Reprocessina Plant, Criterion
- 11. " Quality Assurance Program" b.
Regulatory Guide 1.29 Rev. 2, Seismic Desian Classification, (02/76) t c.
Regulatory Guide 1.26, Rev. 2, Quality Group Classifications j
and Standard for Water-Steam, and Radioactive Weste j
Containing Components of Nuclear Power Plants, (06/75) l d.
SNP FSAR, Section 3.2 (Amendment 3), " Classification of Structures, Systems and Components" e.
SNP FSAR, Section 17 (Amendment 3), " Quality Assurance" 29?l?
f.
TVA Topical Report TVA TR75-1 A (Rev. 8), Quality Assurance ox Program Description for the Desian. Construction, and Operation of TVA Nuclear Power Plants g.
Nuclear Quality Assurance Manual Part V, Section 2.7 (ID-QAP-2.7), Rev. O, "Q-List," (06/18/86) h.
Nuclear Quality Assurance Manual, Appendix A. "CSSC Lists -
All Plants," (07/29/85) 1.
2QPD-5, Rev.1, All Nuclear Plants - The Identification and Specification of items Covered 8v the OEOC Ouality Assurance Program j.
NEP-5.1 Rev. O, Desian Output Attachment 6 "Q-List,"
(07/01/86) k.
Construction Specification, N2G-877 (Rev. 5), Identification of Structure. Systems. and Components Covered by the Seauoyah l
Nuclear Plant Quality Assurance Program 1.
SNP Administrative Instruction, AI-39, Rev. 2, Critical Structures. Systems and_ Components - (CSSC), (01/09/86) m.
SNP Standard Practice, SQA134. Rev. 8. Critical Str_ucture.
Systems and Components (CSSC) List, (01/27/86) t' 0929d (10/16/86)
E TVA EMPLOYEE CONCERNS REPORT NUMBER:
209.1(8)
SPECIAL PROGRAM REVISION NUMBER: 0 f.
PAGE 13 0F 15 APPENDIX A (Cont'd) n.
SQN Generic Concern Task Force Report, GOR 16-16, Rev.1, for Employee Concern Number IN-85-688-003, (06/02/86) o.
NSRS Investigation Report I-85-422-W8N, (10/04/85) p.
WBNP NCR No. W-269-P, (08/26/85) q.
Letter f rom Mills (TVA) to Adensam (NRC), ( A27831107026),
"TVA Docket No. 50-327 & 50-328, TVA Response to Items 2.1 and 2.2 of NRC Generic Letter 83-28," (11/07/83) r.
Letter f rom Arms (TVA) to American Nuclear Insurers, (LO1 841221 158), "SQN-ANI/MAELU Nuclear Liability Insurance
- Sept.10-13,1984 Inspection - Recommendations 84-2, 84-3, and 84-4," (12/19/84) s.
Letter from Olshinski (NRC) to White (TVA), (L44860429173),
" Report Nos. 50-327/86-11 and 50-328/86-11," (04/22/86)
(W (E
t.
Letter f rom Gridley (TVA) to Grace (NRC), (L44860627800),
" Response to Inspection Report 50-307/86-11 and 50-328/86-11," (06/27/86) u.
Minutes of SQN CSSC Review Committee Meetings:
Meeting 85-02, (553 850730 825), (06/26/85)
Meeting 85-03, (S53 851101980), (09/10/85)
Meeting 85-04, (S53 851203 903), (11/14/85)
Meeting 86-01, (553 860219 840), (01/14/86)
Meeting 86-02, (S53 860423 814), (04/15/86)
Meeting 86-03, (S53 860514 940), (04/24/86) v.
TVA memo f rom T. G. Campbell to W. E. Andrews.
(L53840807942), "SQN-CSSC List," (08/09/84) w.
TVA memo f rom Law to Those Listed, (L16 851003 854), "Q-List Specification," (10/03/85)
M TVAmemofromWhitttoParris,(NoRIp),"NSRSInvestigation x.
Report I-85-422-W8N," (10/11/85) y.
TVAmemofromHowardtoEnnis,(NoRI)f$),"EmployeeConcern Investigation Report Transmittal Response," (12/06/85) 0929d (10/16/86)
)
TVA EMPLOYEE CONCERNS REPORT NUMBER:
209.1(B)
SPECIAL PROGRAM REVISION NUMBER: 0 PAGE 14 0F 15 7
i t
APPENDIX A (Cont'd)
TVAmemofromWhitttoEnnis.(NoRI/S),"CorrectiveAction
)
z.
Response Evaluation (I-85-422-WBN, Item 2)," (01/08/06)
)
L aa.
TVA memo from Whitt to Ennis, (No RI
), " Corrective Action
{
Response Evaluation (I-85-422-WBN, ems 1, 3, 4)," (01/08/86) 2 3
bb.
TVA memo from Raulston to Gridley, (845 860306 260), " Final 10CFR50.55(e) Report on NCR W-269-P R1," (03/06/86) 6.
WHAT REGULATIONS. LICENSING COMITMENTS. DESIGN REQUIREMENTS OR OTHER APPLY OR CONTi'OL IN THIS AREA?
a.
10CFR50, Appendix B, Criterion II, " Quality Assurance Program" i
j b.
Regulatory Guide 1.26, Quality Group Classifications and
}
Standards for Water-Steam, and Radioactive Waste Containing Components of Nuclear Power Plants
,O c.
Regulatory Guide 1.29, Seismic Desian Classification d.
SNP FSAR, Section 3.2, " Classification of Structures, 1
Systems, and Components" e.
SNP FSAR, Section 17.0, " Quality Assurance" f.
TVA Topical Report, TVA-TR75-1 A, Quality Assurance Program l
DescriDtion for Design. Construction. and Operation g.
TVA Nuclear Quality Assurance Manual (NQAM), Section 2.7, "Q-List," and Appendix A. "CSSC Lists - All Plants" h.
Nuclear Engineering Procedures (NEP) - 5.1, Design Output 1.
SNP Administrative Instruction, AI-39, Critical Structures, Systems and Components - (CSSC) j.
SNP Standard Practice, SQA134, Critical Structure. Systems, and Components (CSSC) List 0929d (10/16/86)
TVA EMPLOYEE CONCERNS REPORT NUM8ER:
209.l(8)
SPECIAL PROGRAM REVISION NUM8ER: 0 PAGE 15 0F 15 f
APPENDIX A (Cont'd) 7.
LIST REQUESTS FOR INFORMATION. MEETINGS. TELEPHONE CALLS. AND OTHER DISCUSSIONS RELATED TO ELEMENT.
j a.
Request for Information (RFI), SQN-563, (09/15/86) b.
RFI, SQN-564, (09/15/86)
?
c.
RFI, SQN-576, (09/18/86)
J d.
RFI, SQN-583, (09/22/86) e.
Telecon, L. J. Anderson (Bechtel), with R. W. Fortenberry (TVA),10M-258, (09/18/86)
(b9/h4 6 g.
Telecon, L. J. Anderson (Bechtel), with D. T. Clift (TVA),
10M-273,(09/29/86)
~
h.
Telecon, L. J. Anderson (Bechtel), with D. T. Clif t/R. Olson (TVA), 10M-306, (10/09/86) 1.
Telecon, L. J. Anderson (Bechtel), with D. T. Clift /R. W.
Fortenberry (TVA),10M-308, (10/09/86) f i
0929d (10/16/86) i
1,
.a ECTG C.3 Attachment A Page 1 of 1 Revision 2 - A ECSP CORRECTIVE Action Tracting Document (CATD)
INITIATION 1.
Imusediate Corrective Action Required: k Yes O No 2.
Stop Wort Recomunended: 0 Yes M No SdN
-\\
4 INITIATION DATE 10MG/E 3.
CATD No. l)DT.l 5.
RESPONSIBLE ORGANIZATION:
DNP [offeATitAls) /'P4E 6.
PROBLEM DESCRIPTION: MR O NQR TVA has e o A FeWea et & SGN Cf5C LAf fe CMrm Tir hera-nu Ad 'comalatentM. In slAtlin-Yektare la SQA CSFC Reseu Co u dr/e m,eh'.,nrmfer indvider +G -#*A ach rtone AsterlM rd& "dfrerminh crund.- Circ c andtrakw have been dtFtratA 4s 4ke mud;u DGF' (2 Lid oui ma,k. Jess o pr e Mr&
der id4 amenlL e4' rsanssa A A 4ta0 La emef' rd 494 M M am^
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O ATTACHMENTS
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1.
PREPARED BY: NAME ME E-m DATE: 104te/ff, 8.
CONCURRENCE: CEG-H N Y h A M AnF DATE: //- / W 9.
APPROVAL: ECTG PROGRAW iGR. ' ' /
DATE:
i 8
CORRECTIVE ACTION 10.
PROPOSED CORRECTIVE ACTION PLAN:
[g O ATTACHMENTS 11.
PROPOSED BY: DIRECTOR /MGR:
DATE:
12.
CONCURRENCE: CEG-H:
DATE:
SRP:
DATE:
ECTG PROGRAM MGR:
DATE:
VERIFICATION AND CLOSEOUT 13.
Approved corrective actions have been verified as satisfactorily implemented.
SIGNATURE TITLE DATE i
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