ML20209C311
| ML20209C311 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/23/1987 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20209C049 | List: |
| References | |
| 209.1(B), 209.1(B)-R01, 209.1(B)-R1, NUDOCS 8702040244 | |
| Download: ML20209C311 (20) | |
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,j TVA EMPLOYEE CONCERNS REPORT NLMBER: 209.1(B)
SPECIAL PROGRAM REPORT TYPE: SEQUOYAH ELEMENT REVISION NLMBER: 1 TITLE: Q-LIST Q-List Differences PAGE 10F 19 REASON FOR REVISION: -
- 1. Revised to incorporate SRP and TAS comments, add chronology, and add Section 10, Corrective Action.
PREPARATION PREPARED :
A 0' / f $7 SIGNATURE / DATE REVIEWS 3EER: REVIEW CalMITTEE:
h'^ I* 16 #E7
! SIGNATURE / y'~' DATE TAS ^~"i^
A 11lor US*$l 7/ SIGNATURE DATE CONCURRENCES 8702040244 870127 - ,
p A 0500 g7 CEG-H: / /4U SRP:,_ ,u,ug LUh)dC / -2 3 4~7 SIGNATURE DATE SIGNATURE DATE APPROVED M & k' BY:?db itwr six DATE ECSP MANAGtR DATE / MANAGER OF NUCLEAR POWER CONCURRENCE (FINAL REPORT ONLY)
.. TVA EMPLOYEE CONCERNS REPORT NLMBER: 209.l(B)
SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 2 0F 19
- 1. CHARACTERIZATION OF ISSUE (S):
Concern: Issues:
IN-85-407-001 a. The documents (Q-Lists or equivalent)
"CSSC 0-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 infomation." priate QA program controls on items l 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
'O' 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.)
- 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.
mer.ts (CSSC) 'Q' List. Many items originally placed on the NUC Power 'Q' List are not reflected on the CSSC 'Q' List, j which could adversely affect
! establishment of appropriate quality controls on items which are related to plant safety.
Nuclear Power concern. No specifics provided. CI has no further infomation."
IN-86-090-001 "NUC PWR (No name/ dept. given) issued a Critical Structures, Systems and Components List (CSSC) that does not include all 0929d (01/15/87) l -_- . .
,. TVA EMPLOYEE CONCERNS REPORT Nt4SER: 209.1(B)
SPECIAL PROGRAM REVISION NLMBER: 1 PAGE 3 0F 19 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 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 N0 Identified by TVA SQN Generic Task Force (GCTG)
Date June 2,1986 Documentation Identifiers: G0R-16-16, Rev.1 Report G0R-16-16, Rev.1 documents results of an investigation for SQN of Concern Number IN-85-688-003.
- 3. DOCtMENT NOS., TAG NOS., LOCATIONS, OR OTHER SPECIFIC DESCRIPTIVE IDENTIFICATIONS STAltu IN ELtatNT.
None
- 4. INTERVIEW FILES REVIEWED:
- a. Expurgated file for IN-85-688-003. This file contained a l copy of the Employee Concern "K" fom, and a brief expurgated interview statement with no additional information.
- b. Expurgated file for IN-86-090-001. This file contained a copy of the Employee Concern "K" fom, and copies of l documents previously reviewed by this evaluator.
- c. Expurgated file for IN-85-407-001. This file contained l copies of the Employee Concern "K" fom, ECTG Administrative forms, and documents previously reviewed by this evaluator.
- d. Expurgated file for IN-86-087-004. This file contained copics of the Employee Concern "K" form, ECTG administrative foms, and documents previously reviewed by this evaluator.
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',. TVA EMPLOYEE CONCERNS REPORT NUMBER: 209.1(B)
SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 4 0F 19
- 5. DOCUMENTS REVIEWED RELATED TO THE ELEMENT:
See Appendix A.
- 6. WHAT REGULATIONS, LICENSING COMMITMENTS, DESIGN RE0UIREMENTS, OR OTHER APPLY OR CONTROL IN THIS AREA 7 See Appendix A.
- 7. LIST REQUESTS FOR INFORMATION, MEETINGS, TELEPHONE CALLS, AND OTHER DISCUSSIONS RELAltu TO ELEMENT.
See Appendix A.
- 8. EVALUATION PROCESS:
- a. Determined the use of Q-Lists (or equivalent) on SQN as the method for identifying which items require QA program controls,
- b. Reviewed the procedures and practices governing the methods determined in "a."
- c. Revi,ewed the implementation of procedures and practices in
- d. Evaluated the adequacy of this information to resolve the issues associated with this element.
- 9. DISCUSSION, FINDINGS, AND CONCLUSIONS:
Chronology:
05/70: Construction pennit issued for SQN Units 1 and 2 03/77: Construction Specification N2G-877 provides additional instruction to Construction for identifying safety-related structures, systems, and components 0929d (01/15/87)
.. TVA EMPLOYEE CONCERNS REPORT NIMIER: 209.1(B)
SPECIAL PROGRAM REVISION NLMBER: 1 PAGE 5 0F 19 04/78: The CSSC List developed and issued by Nuclear Power for the Operations QA program 09/80: Operating license issued for SQN Unit 1 0 9 /81 : Operating license issued for SQN Unit 2 10/82: OEDC-2QPD-5 Rev.1 assigns EN DES the responsibility of preparing a detailed identification of structures, systems, and components covered by the QA program (Q-List) 01 /8 3 : Office of Engineering (OE) issues the WBN Q-List for 1 year trial use 01 /8 5: Discrepancies surface among the various WBN Q-Lists, leading to issue of NCR W-269-P in 08/85 and subsequent reporting to the NRC as a 10CFR50.55(e)
"significant deficiency" in 10/85 02/85: Responsibility for maintaining the SQN CSSC List transferred to the Site Director from QA organization 03/85: SQN Administrative Instruction AI-39 provides for maintenance of the SQN CSSC List by the CSSC Review Conunittee 06/85: Employee Concern IN-85-407-001 received by TVA 07/85: Employee Concern IN-85-688-003 received by TVA 08/85: Employee Concerns IN-86-087-004 and IN-86-090-001 received by TVA 06/86: SQN Generic Concern Task Force issues Report GOR-16-16 Rev.1, Investigation of Employee Concern IN-85-688-003 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 l the lists, and the impact of using those lists. Al though l
l 0929d (01/15/87) l - _
TVA EMPLOYEE CONCERNS REPORT NUMBER: 209.l(B)
SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 6 0F 19 these concerns resulted from specific applications and conditions at WBNP, they have been classified as generically 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 identificaticn, 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 i
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 Operations organization; the list was not used by Construction or Engineering on SQN.
The SQN CSSC List identifies those structures, systems, and components committed in the SQN FSAR Section 3.2 as necessary to assure:
- 1. The integrity of the reactor coolant pressure boundary.
- 2. The capability to shut down the reactor and maintain it in a safe shutdown condition.
- 3. .The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the guideline exposures of 10 CFR Part 100.
The individual system drawings (P& ids, flow diagrams, etc.)
developed by Engineering also identified the safety-related structures, systems, and components on SQN. These drawings, rather than the SQN CSSC List, were used by the Construction organization as the source documents to determine the items that required QA program controls.
0929d (01/15/87)
TVA EMPLOYEE CONCERNS REPORT NLDSER: 209.l(B)
SPECIAL PROGRAM REVISION NLSWER: 1 PAGE 8 0F 19 contained in Sequoyah Standard Practice SQA-134. 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 Comittee to maintain the SQN CSSC List. AI-39 cites the following pertinent requirements and responsibilities for the SQN CSSC Review Comittee:
o Membership consists of a designated representative from each of the following groups:
Engineering Group - Chainnan Administrative Services - Secretary Regulatory Engineering Quality Assurance Maintenance (Instrument, Electrical, Mechanical)
Design Services (DNE involvement provided on an as-needed basis) o The comittee is required to meet at least once per quarter.
[
o Meeting results are documented, and recommended changes to the CSSC List are submitted for Plant Operations Review Comittee (PORC) review and Plant Manager's approval o The comittee is required to perform a biennial review of the CSSC List to ensure that the list is accurate and complete
- e. The review of reference documents identified various cases of direct or inferred concern regarding the accuracy and completeness of the CSSC List, including the following:
o Authorized Nuclear Inspector (ANI) inspection of SQN l dated September 10-13,1984, ( App. A, 5.r) recomended, "The safety-related equipment list should be reviewed periodically for completeness and accuracy by the cognizant group. Additionally, the Office of Quality Assurance (QA) should ensure an adequate review through the audit process."
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.. TVA EMPLOYEE CONCERNS REPORT MER: 209.l(8) l SPECIAL PROGRAM 2
REVISION M ER: 1 ;
- PAGE 9 0F 19 i
o The Office of Engineering, Design, Construction I document, OEDC-2QPD-5, ( App. A, 5.1), established the commitment for Engineering to prepare a Q-List for each 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 i time (1982).
o SQN CSSC Review Committee Meeting Minutes ( App. A, 5.u) contain agenda items that imply that the completeness and accuracy of the existing CSSC List is indeterminate, for example: "Detemine accuracy of SQN CSSC List for instruments and controls and revise the CSSC List as requi red."
l (Note: The evaluator was infomed ( App. A, 5.ee) that there were extenuating circumstances for the cited agenda item - that discrepancies identified in the
! instruments and controls CSSC List in 1981, had been resolved in 1982, and this agenda item had been left open in order to check the I&C list against the j
forthcoming Q-list when issued.)
l o SQN Generic Concern Task Force Report GOR 16-16 ( App. A, 5.n) contains reconnendations which include: "A timely review for completeness and accuracy should be conducted 1
to ensure the adequacy of the 'CSSC' List as connitted I to in the response to ANI, dated December 19, 1984, i
letter (L64 850104 303)."
The review of case file documents indicated that a complete review of the SQN CSSC List had not been accomplished to date. Minutes of CSSC Review Connittee meetings ( App. A, l
' 5.u) reflected that the connittee perfomed 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.
l f. There are indications-(listed below) that action items 4
associated with the SQN CSSC List are being deferred to the pending DNE Q-List development.
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.. TVA EMPLOYEE CONCERNS REPORT NLSSER: 209.1(B)
SPECIAL PROGRAM REVISION NtSSER: 1 PAGE 10 0F 19 l o The TVA conunf tment to review the SQN CSSC List for accuracy and completeness on a biennial basis appears to the evaluator to be an action drifting towards deferral to the pending Q-List completion,
- o. The CSSC Review Conunf ttee 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 commitment 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 after 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 classification of these items in 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 I
are documented in GCTF Report GOR 16-16 ( App. A, 5.n), which states that the scope of that investigation was "To detemine 4
if the CSSC List used for Sequoyah is accurate."
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] The evaluator considers that the conclusions and L
reconenendations stated in GCTF Report GOR 16-16 are somewhat l i l contradictory and inconclusive, in that Section IV A.1 states as a conclusion:
"The issue was detemined not to be valid by this investigation bec'ause . . .Sequoyah is using an accurate
< 'CSSC List' developed by Quality Assurance and not the
'Q-List' developed by the Office of Engineering." l 0929d (01/15/87)
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, TVA EMPLOYEE CONCERNS , ' REPORT NtM8ER: 209.1(B)
- SPECIAL PROGRAM REVISION NtMBER
- 1 PAGE 110F 19 While Section IV B.1 states as a recommendation:
"A timely review for completeness and accuracy should be conducted to ensure the adequacy of the..'CSSC' List as
, cannitted 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) docuents NRC inspection activities associated with followup of TVA's response to NRC Generic Letter. 83-28 (App. A, 5.q). Sections 2.1 and 2.2 of GL83-28 contain requirements for licensees to confim the safety-related identification of components of the reactor trip system, and to describe their program for ensuring that all camponents 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 doc u ents 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 4
tracking CSSC Review Cannittee agenda items, and for requesting changes to the CSSC List. TVA's response (App. A, 5.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 detemined that there were no violations or deviations.
Findings:
- to identify items that require QA program controls. Although i a review of the SQN CSSC List for accuracy and completeness
! has been cammitted to by TVA, such a review has not been perfomed to date. The requirement to perfom a biennial review of the CSSC List is presently scheduled for completion by June 1987.
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.. TVA EMPLOYEE CONCERNS REPORT NLSEER: 209.1(B) l SPECIAL PROGRAM REVISION NIMBER: 1 PAGE 12 0F 19 The activities of the SQN CSSC Review Committee, are a positive factor towards maintaining the SQN CSSC List as a "living" document. However, the following shortco;aings are evident in the Review Comittee actions:
o A TVA review of the SQN CSSC List for accuracy and completeness has not been accomplished to date.
Therefore the baseline, to which the CSSC Review Comittee is providing updates for plant modifications etc., is of undetermined accuracy and completeness.
o The practice of deferring numerous classification actions to the pending DNE Q-List development, contributes to the questionable status of SQN CSSC List accuracy and completeness.
- b. The investigation indicated that only a single listing, the SQN CSSC List, was used on Seguoyah. 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 comitment to implement the forthcoming DNE-developed and maintained Q-List will adhere to the principle that a single list prescribing QA program applicability will be in existence for SQN. Thus, at some future date, the SQN CSSC List will apparently be superseded by an SQN Q-List.
l 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 Comittee. Although direct DNE organization membership on the comittee is not prescribed by the controlling procedure (AI-39), DNE has actively participated in CSSC Review Comittee activities on an as-needed basis. The interface with DNE tempers the employee concern related to the issue of lack of engineering design group input / approval of the CSSC List, and indicates a DNE "de facto" involvement with the list.
l 0929d (01/15/87)
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- TVA EMPLOYEE CONCERNS REPORT Nt2EER: 209.l(B)
SPECIAL PROGRAM REVISION Nt2EER: 1 N PAGE 13 0F 19 0
Conclusions:
- a. The evaluation team considers the issues relating to the accuracy and completeness of the SQN CSSC List to be valid for SQN. This conclusion is tempered by the positive factor
, that the on-going activities of the SQN CSSC Review Committee provide a reasonable assurance that there are not major problems with the SQN CSSC List. However, it is prudent for TVA to perform a confimatory review of the accuracy and completeness of the SQN CSSC List, to address various TVA internal references (direct or inferred) to the need for such a review. The review should be perfomed with input from DNE to detemine the degree of completeness appropriate for the list, and should include; resolution of those agenda items previously deferred by the SQN CSSC Review Comittee.
- b. The issues relating to the existence of multiple Q-Lists (or equivalents) with different contents are not valid for SQN.
- c. The issues related to the lack of engineering design group input to the Q-lists (or equivalents) are not valid for SQN.
- 10. CORRECTIVE ACTION:
TVA has submitted a corrective action plan (TCAB-022) which was reviewed by the evaluation team and discussed with the responsible line organization. The discussions clarify the corrective action plan and were documented via letter ( App. A, 7.j and k).
The corrective action plan comits that all active items on the SQN CSSC Review Comittee agenda will be reviewed to identify any items that require actions prior to restart. This review will include those items that.were noted as " deferrals to the development of the Q-List."
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,. TVA EMPLOYEE CONCERNS REPORT NUMBER: 209.1(B)
SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 14 0F 19 In addition to the above review action, the corrective action plan submitted by TVA provided additional information regarding DNE involvement with the CSSC Review Committee activities, and further justification that a complete review of the CSSC List is not necessary prior to restart. That additional information has been incorporated as appropriate into Section 9 of this evaluation report.
The evaluation team concurs with the TVA corrective action plan.
0 0929d (01/15/87)
' TVA EMPLOYEE CONCERNS REPORT NIM 8ER: 209.1(8)
SPECIAL PROGRAM REVISION NLMBER: 1 PAGE 15 0F 19 APPENDIX A
- 5. DOCLMENTS REVIEWED RELATED TO THE ELEMENT:
- a. 10CFR50, Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plant, Criterion II,
" Quality Assurance Program"
- b. Regulatory Guide 1.29 Rev. 2, Seismic Design Classification, (02/76)
- c. Regulatory Guide 1.26, Rev. 2, Quality Group Classifications and Standard for Water-Steam, and Radicactive Waste Containing Components of Nuclear Power Plants, (06/75)
- d. SNP FSAR, Section 3.2 (Amendnent 3), " Classification of Structures, Systems and Components"
- e. SNP FSAR, Section 17 (Amendnent 3), " Quality Assurance"
- f. TVA Topical Report, TVA TR75-1A (Rev. 8), Quality Assurance Program Description for the Design, 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 By the OEDC Quality Assurance Program
- j. NEP-5.1 Rev. O, Design Output, Attachment 6 "Q-List,"
(07/01 /86)
- k. Construction Specification, N2G-877 (Rev. 5), Identification of Structure, Systems, and Components Covered by the Sequoyah Nuclear Plant Quality Assurance Program
- 1. SNP Adninistrative Instruction, AI:39, Rev. 2, Critical Structures, Systems and Components - (CSSC), (01/D9/86) 0929d (01/15/87)
. TVA EMPLOYEE CONCERNS REPORT NLMBER: 209.1(B)
SPECIAL PROGRAM REVISION NLMBER: 1 PAGE 16 0F 19 APPENDIX A (Cont'd)
- m. SNP Standard Practice, SQA134, Rev. 8, Critical Structure, Systems and Components (CSSC) List, (01/27/86)
- n. SQN Generic Concern Task Force Report, G0R16-16, Rev.1, for Employee Concern Nisnber IN-85-688-003, (06/02/86)
- o. NSRS Investigation Report I-85-422-WBN, (10/04/85)
- p. WBNP NCR No. W-269-P, (08/26/85)
- q. Letter from 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 from Anns (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 01shinski (NRC) to White (TVA), (L44860429173),
" Report Nos. 50-327/86-11 and 50-328/86-11," (04/22/86)
- t. Letter from 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 deview Committee Meetings:
! Meeting 85-02, (S53 850730 825), (06/26/85) l Meeting 85-03, (S53 851101 980), (09/10/85)
! Meeting 85-04, (S53 851201903), (11/14/85)
Meeting 86-01, (S53 800G9 840), (01/14/86) t
. Meeting 86-02, (S53 860423 814), (04/15/86)
Meeting 86-03, (S53 860514 940), (04/24/86)
- v. TVA memo from T. G. Campbell to W. E. Andrews, (L53840807942), "SQN-CSSC List," (08/09/84) l
- w. TVA memo from Law to Those Listed, (L16 851003 854), "Q-List Specification," (10/03/85)
- x. TVA memo from Whitt to Parris, (No RIMS), "NSRS Investigation Report I-85-422-WBN," (10/11/85)
- y. TVA memo from Howard to Ennis, (No RIMS), " Employee Concern l Investigation Report Transmittal Response," (12/06/85) l l 0929d (01/15/87)
TVA EMPLOYEE CONCERNS REPORT Wl#EER: 209.l(B)
SPECIAL PROGRAM l REVISION NtBSER: 1 PAGE 17 0F 19 l
APPENDIX A (Cont'd)
- z. TVA memo from Whitt to Ennis, (No RIMS), " Corrective Action !
Response Evaluation (I-85-422-WBN, Item 2)," (01/08/86) '
aa. TVA memo from Whitt to Ennis, (No RIMS), " Corrective Action Response Evaluation (I-85-422-WBN, Items 1, 3, 4)," (01/08/86) bb. TVA memo from Raulston to Cridley, (B45 860306 260), " Final 10CFR50.55(e) Report on NCR W-269-P R1," (03/06/86) cc. TVA memo from Fortenberry to McNutt, (No RIMS), "SQN -
Engineering Related Em 209.1(B) and 209.2(B),gloyee Concerns - Subcategory / Element (10/06/86) dd. TVA memo from Abercrombie and Brown, (S03 861205 808), "SQN -
ECTG Element Report 209.01 SQN - Engineering Category -
Corrective Action Plan (CAP)," (12/05/86) ee. Letter from McNutt to Parkinson, (TCAB-022), " Employee Concern Evaluation Program - Sequoyah Restart Program -
Corrective Action Plan (CAP)," (12/08/86) ff. TVA memo from Fortenberry to Clift, (No RIMS), "SQN -
Employee Concern - Element 209.1 - CSSC List," (12/18/86) gg. TVA memo from Fortenberry to McNutt, (SS3 870106 942), "SQN -
Employee Concern Evaluation Report - SQN Element Report 209.1(B)," (01/05/87)
- 6. WHAT REGULATIONS, LICENSING C0pWITMENTS, DESIGN REQUIREMENTS OR OTHER APPLY OR CONTROL IN THIS AREA?
- a. 10CFR50, Appendix B, Criterion II, " Quality Assurance Program"
- b. Regulatory Guide 1.26, Quality Group Classifications and Standards for Water-Steam, and Radioactive Waste Containing Components of Nuclear Power Plants
- c. Regulatory Guide 1.29, Seismic Design Classification
- d. SNP FSAR, Section 3.2, " Classification of Structures, Systems, and Components"
- e. SNP FSAR, Section 17.0, " Quality Assurance" 0929d (01/15/87)
TVA EMPLOYEE CONCERNS REPORT Nt#RER: 209.l(B)
SPECIAL PROGRAM REVISION NLSEER: 1 PAGE 18 0F 19 APPENDIX A (Cont'd)
- f. TVA Topical Report, TVA-TR75-1 A, Quality Assurance Program Description 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
- i. SNP Administrative Instruction, AI-39, Critical Structures, Systems and Components - (CSSC)
- j. SNP Standard Practice, SQA134, Critical Structure, Systems, and Components (CSSC) List
- 7. LIST REQUESTS FOR INFORMATION, MEETINGS, TELEPHONE CALLS, AND OTHER NETU53 IONS RELAltu TO ELEMENT.
- a. Request for Information (RFI), SQN-563, (09/15/86)
- b. RFI, SQN-564, (09/15/86)
- c. RFI, SQN-576, (09/18/86)
- d. RFI, SQN-583, (09/22/86)
- e. Telecon, L. J. Anderson, Bechtel, with R. W. Fortenberry, TVA, IOM 258, (09/18/86)
- f. Telecon, L. J. Anderson, Bechtel, with D. T. Clift, TVA, IOM 272, (09/24/86)
- g. Telecon, L. J. Anderson, Bechtel, with D. T. Clift, TVA, IOM 273, (09/29/86)
- h. Telecon, L. J. Anderson, Bechtel, with D. T. Clift /R. Olson, l TVA, IOM 306, (10/09/86)
- 1. Telecon, L. J. Anderson, Bcchtel, with D. T. Clift /R. W.
Fortenberry, TVA, IOM 308, (10/09/86)
- j. Telecon, L. J. Anderson /R. W. Wolters/J. B. Violette, Bechtel, and D. T. Clift /R. W. Fortenberry, TVA, IOM 520, (12/17/86)
- k. Letter, G. L. Parkinson, Bechtel to G. R. McNutt, TVA, BLT 084, (12/23/86)
- 1. Letter, G. L. Parkinson, Bechtel, to G. R. McNutt, TVA,
- BLT-097, (01/15/87) l 0929d (01/15/87)
. TVA EMPLOYEE CONCERNS REPORT NLMBER: 209.1(B)
SPECIAL PROGRAM REVISION NLMBER: 1 PAGE 19 0F 19 CATD LIST The following CATD identifies and provides corrective actions for the findings included in this report:
209.01 SQN 01 (12/05/86) l
(
0929d (01/15/87)
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REFERENCE - ECPSI20J-ECPS121C TENNESSEE VALLEY AUTHORITY PAGE -
70
- REQUEST OFFICE OF NUCLEAR P0HER RUN TIME - 12:57:19
) FREQUENCY ONP - ISSS - RHM EMPLOYEE CONCERN PROGRAM SYSTEM (ECPS) RUN DATE - 12/02/86 5 LIST OF EMPLOYEE CONCERN INFORMATION CATEGORY: EN DES PROCESS & OUTPUT SUBCATEGORY: 20901 Q-LIST DIFFERENCES
) S GENERIC KEYWORD A b H APPL QTC/NSRS P KEYHORD B CONCERN SUB R PLT 5BSH INVESTIGATION S CONCERN KEYNORD C CAT D LOC FLQB REPORT R DESCRIPTION KEYNORD D
,)
. NUMBER CAT .g IN 407-001 EN 20901 S HBN YYYN I-85-422-HBN SS CSSC Q-LIST I NOT ACCURATE. NOT ALL DOCUMENTS T50098 EN 20902 K-FORM COMPONENTS COVERED BY QA PROGRAM AR CLASSIFICATION E LISTED, QE DEPARTMENT HAS LIST THA QUALITY ,)
- 5) T DOCUMENTS THE INACCURACIES. THE C GENERAL SSC Q-LIST IS USED TO DETERMINE IF Q C INSPECTIONS ARE REQUIRED. CI HAS NO FURTHER INFORMATION.
-)
IN 688-003 EN 20901 N HBN YYYN I-85-422-HBN SR CONCERN OVER VALIDITY OF CRITICAL SY DOCUMENTS T50080 K-FORM STEM, STRUCTURES AND COMPONENTS "Q" NONCONFORMANCE LISTING. DETAILS KNOHN TO QTC. DET QUALITY
) AILS HITHHELD TO MAINTAIN CI CONFIDE HTIALITY.
REPORTS 2)
EN 20901'S HBN YYYN I-85-422-HBN SS SIGNIFICANT DIFFERENCES EXIST IN THE DOCUMENTS
) IN 087-004 T50120 EN 20902 K-FORM CONTENT OF THE NUCLEAR PONER "Q" LI NONCONFORMANCE I)
ST AND THE CRITICAL STRUCTURES, SYST QUALITY-EMS AND COMPONENTS (CSSC) "Q" LIST. GENERAL MANY ITEMS ORIGINALLY PLACED ON THE
-) NUC POWER "Q" LIST ARE NOT REFLECTE $s D ON THE CSSC "Q" LIST, HHICH COULD ADVERSELY AFFECT ESTABLISHMENT OF AP PROPRIATE QUALITY CONTROLS AN ITEMS 3 HHICH ARE RELATED TO PLANT SAFETY. 'd NUCLEAR PDHER CONCERN. NO SPECIFICS PROVIDED, CI HAS NO FURTHER INFORMA TION.
3 IN 090-001 EN 20901 S HBN YYYY I-85-422-HBN SS NUC PHR (NO NAME/ DEPT GIVEN) ISSUED DOCUMENTS T50120 EN 20902 REPORT A CRITICAL STRUCTURES, SYSTEMS & COM NONCONFORMANCE QA 80608 PONENTS LIST (CSSC) THAT DOES NOT IN GENERAL ,
> CLUDE ALL ITEMS IDENTIFIED ON THE SI MATERIAL q TE "0" LIST (NO SPECIFICS GIVEN) . T HIS HAS DONE HITHOUT OFFICE ON ENGG, ENGG DESIGN GRP INPUT / APPROVAL (THE J ORIGINATOR OF THE SITE "Q" LIST). R BY REFERRING TO THE CSSC, THE POSSIB
"" ILITY EXISTS FOR INSTALLING "NON-Q" ITEMS IN A SAFETY-RELATED SYSTEM. C 3 I HAS NO ADDITIONAL INFORMATION. NU <
C P0HER CONCERN 4 CONCERNS FOR CATEGORY EN SUBCATEGORY 20901 1
> k
,