ML20209D725
| ML20209D725 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/27/1987 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20209B481 | List: |
| References | |
| 213.3(B), 213.3(B)-R01, 213.3(B)-R1, NUDOCS 8702040535 | |
| Download: ML20209D725 (16) | |
Text
-, _ -
TVA EMPLOYEE CONCERNS REPORT NUMBER:
213.3 (B)
SPECIAL PROGRN4 REPORT TYPE:
SEQUOYAH ELEMENT REVISION NUMBER: 1 1
TITLE:
ELECTRICAL PROCEDURES Inadequate Electrical Design Criteria.
Inadequate Consideration Given to PAGE 10F 15 Electrical Standards and Guides REASON FOR REVISION:
1.
Revised to incorporate SRP and TAS coments and to add Section 10, Corrective Action.
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ECSP MANAGER DATE MANAGER OF NUCLEAR POWER DATE CONCURRENCE (FINAL REPORT ONLY) l
- SRP Secretary's signature denotes SRP concurrences are in files.
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TVA EMPLOYEE CONCERNS REPORT NUMBER: 213.3 (B)
SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 2 0F 15 1.
CHARACTERIZATION OF ISSUE (S):
Concern:
Issues:
WI-85-100-019 a.
Standards and guides are not incor-
" Electrical Standards and Guides porated into the electrical design are treated as guides, and are criteria.
not incorporated in design criteria requirements. Electri-b.
Sufficient electrical design cal design criteria, where it criteria to form a basis for exists, is not complete, is design are nonexistent.
vague, and in general is inadequate."
c.
Electrical design criteria are inadequate to form a basis for design.
The following issues from this concern are addressed in other reports:
Standards are treated as guides (addressed in Sequoyah Element Report 201.4).
There appears to be programmatic inadequacy with regard to preparation and adequacy of design criteria (addressed in Sequoyah Element Reports 201.3 and 201.4).
P.
HAVE ISSUES BEEN IDENTIFIED IN ANOTHER SYSTEMATIC ANALYSIS? YES X N0 o
Identified by Gilbert / Commonwealth Inc.
Date 03/03/86 Final Report No. 2614, " Technical Review of SQN Modifications" 3.
DOCUMENT NOS., TAG NOS., LOCATIONS OR OTHER SPECIFIC DESCRIPTIVE IDENTIFICATIONS STAltu IN ELEMENT:
Electrical design criteria in general.
03100 (01/19/27)
TVA EMPLOYEE CONCERNS REPORT NUMBER:
213.3 (B)
SPECIAL PROGR#1 REVISION NUMBER:
1 PAGE 3 0F 15 4.
INTERVIEW FILES REVIEWED:
File WI-85-100 was reviewed, and no additional unreviewed information for SQN was found for this concern in this report.
5.
DOCUMENTS REVIEWED RELATED TO THE ELEMENT:
See Appendix A.
6.
WHAT REGULATIONS, LICENSING COP 94IlNENTS, DESIGN REQUIREMENTS, OR OTHER APPLY OR CONTROL IN THIS AREA?
See Appendix A.
7.
LIST REQUESTS FOR INFORMATION, MEETINGS, TELEPHONE CALLS, AND OTHER DyCUSSIONSRELATEDTOELEMENT.
See Appendix A.
8.
EVALUATION PROCESS:
a.
Established requirements for the existence of design criteria both historically and currently (review of regulations and TVA procedures).
b.
Determined to what extent TVA (on SQN) has complied, is in compliance, or will comply with these requirements.
c.
Reviewed available transcripts of NRC investigative interviews for additional infonnation regarding this concern, d.
Reviewed existing design criteria for adequacy and for reference to, adoption of, or compliance with design standards and/or guides, e.
Reviewed existing reports, plans, and previously taken corrective actions for adequacy.
f.
Reviewed existing TVA Construction, QA/QC, Operations, and Material Control reports for the Employee Concerns Special Program for applicability to the concerns discussed in this report.
0310D (01/19/8/)
TVA EMPLOYEE CONCERNS REPORT NUMBER:
213.3 (B)
SPECIAL PROGRAM REVISION NLMBER: 1 PAGE 4 0F 15 9.-
DISCUSSION, FINDINGS, AND CONCLUSIONS:
Chronology:
11/85:
Employee concern received by TVA 03/03/86:
Gilbert Commonwealth Inc. report cites inadequacies with regard to design criteria 05/01/86:
TVA establishes design baseline verification program (DBVP) 08/11/86:
J. F. Cox, TVA, memo states: DBVP essentially complete Discussion:
The concerned individual (CI) questions the existence and adequacy of electrical design criteria.
Further, the CI asserts that guides and standards are not incorporated into design criteria and are therefore not required to be followed.
Finally, the general issue of programmatic inadequacy with regard to the preparation of design criteria is raised.
The intended purpose of design criteria is to establish the engineering requirements that are the basis for conceptual and detailed design.
Design criteria are used in making design decisions, accomplishing design verification, and evaluating design changes. The criteria should include, interpret, and amplify design commitments made in licensing documents, applicable industry standards, and NRC requirements. Additionally, the criteria should specify major functional requirements, environmental constraints, and any system interface requirements.
During the period of the initial design and construction of SQN, there were no industry-accepted requirements for formal design criteria documents.
However, design commitments were reflected in the PSAR, Westinghouse Power Division Standards, and other project documents.
At that time, the governing procedure was Quality Assurance Procedure SQN-QAP-III-1.1 ( App. A, 5.q; 01/30/70),
l
" Preparation and Review of Design Criteria for Sequoyah Nuclear Plant," subsequently, Engineering Procedure (EP) EN DES-EP 3.01 R0
" Design Criteria Documents - Preparation, Review and Approval" was issued ( App. A, 5.h; 07/18/74). This procedure required all l
nuclear projects to prepare design criteria, and endorsed ANSI 45.2.11-1974 (Regulatory Guide [RG] 1.64).
Revision 5 of EN DES-EP 03100 (01/19/87)
4 TVA EMPLOYEE CONCERNS REPORT NUMBER: 213.3 (B)
SPECIAL PROGRAM.
REVISION NUMBER: 1 PAGE 5 0F 15 3.01 (12/13/82) exempted plants earlier than Bellefonte (including SON) from the requirements of the EP.
However, with the issuance cf Office of Engineering Procedure OEP-06 ( App. A, 5.g; 04/26/86)
" Design Input," which superseded EN DES-EP 3.01, SQN was again required to produce design criteria documents.
Finally, OEP-06 was replaced by Nuclear Engineering Procedure (NEP) 3.2 R0 ( App. A, 5.f) " Design Input" on 07/01/86. NEP 3.2 R0 is the procedure l
currently in force, and it is applicable to the SQN project.
l In early 1986, Gilbert / Commonwealth Inc. (G/C) performed a technical review of SQN modifications and concluded that the design criteria were " fragmented." G/C found that TVA had committed to various criteria and standards through responses to NRC evaluations, FSAR references, various memoranda, and generic design criteria, but did not have a complete, up-to-date set of design criteria documents in a system / structure format that reflected these commitments. This led to difficulty in establishing design bases for plant modifications.
Acknowledging these deficiencies, which are similar to the issues of the employee concern (received by TVA 11/85), TVA established the Design Basis Document Program (DBDP, App. A, 5.1; 04/08/E6) to update the design criteria documents and capture licensing commitments and regulations. This program is in conjunction with the overall Design Baseline and Verification Program (DBVP, App. A, 5.i; 05/01/86).
These programs will be conducted in accordance with NEP 3.2, which provides for format, content, preparation, and approval of design criteria. Additionally, NEP 3.2 provides for the use of commitment / requirement (C/R) data sheets to identify commitments or requirements made in other documents (e.g., FSAR, neroranda, letters), and to ensure that these C/Rs are incorporated into the appropriate design criteria. Sequoyah engineering procedure 29 R1 " Procedure for Preparing the Design Basis Document for Sequoyah Nuclear Plant," issued on 07/18/86 ( App. A, 6.d),
provides for the implementation of the DBDP for SQN in accordance with NEP 3.2.
The evaluation team reviewed several electrical design criteria (App. A, 5.k).
This review was performed using RG 1.64 and Engineering Procedures (NEP, OEP, EP) as the acceptance basis.
The criteria appeared to be in compliance with the intent of the Engineering Procedures issued over the years. Moreover, the criteria revised or issued after the issuance of NEP 3.2 are in compliance with the NEP.
In general, adequate reference is made to appropriate standards, codes, guides, and regulations in both the reference sections and in discussion portions.
The criteria reviewed were found to be adequate and sufficient to form a design 0310D (01/19/87)
TVA EMPLOYEE CONCERNS REPORT NUMBER:
213.3 (B)
SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 6 0F 15 basis with some exceptions identified in the separation criteria, SQN-DC-Y-12.1 R6.
These separation criteria deficiencies are discussed in detail in Sequoyah Element Report 242.0 " Electrical Separation."
Most of the design criteria reviewed have been revised to incorporate additional commitments and requirements identified by the C/R data sheets as part of the DBVP.
SQEP 29 provides for closure of C/R data sheets when design criteria are issued.
Ibwever, a sample review of C/R data sheets by the evaluation team indicates that not all C/R data sheets that should be incorporated are included in the appropriate design criteria.
Examples of these are separation criteria that have outstanding C/R data sheets.
(A detailed verification for C/R data sheet incorporation was performed only for the separation criteria.)
Furthermore, there are C/R data sheets which identify commitments and requirements for subjects that are not covered in design criteria and, therefore, have nowhere to be incorporated.
Included in these are the C/R data sheets which identified commitments of FSAR Chapter 7 on instrumentation, and commitments of FSAR Chapter 9 concerning lighting and communications.
Finally, the evaluator was unable to obtain an actual status list with regard to the disposition of C/R data sheets, or any plans for tracking the closeout of this task.
To investigate the issue of the existence of all necessary design criteria, the SQN Design Criteria Manual index was reviewed.
This revealed that criteria exist for the major electrical systems (i.e., APS,125 V dc, vital ac) and also for specialty systems such as Post-Accident Monitoring (PAM).
However, the evaluator was unable to verify existence of design criteria for:
o Overall plant security o
Instrumentation and controls (I&C) o Communications o
Lighting Additionally, there are several design criteria identified in the index which have never been issued.
These unissued criteria are:
o SQN-DC-V-9.7,
" Emergency Operations Facility" o
SQN-DC-V-9.11, " Safety Related Display Instrumentation" o
SQN-DC-V-10.6, "The Dnergency Fire Protection Communications Systems" o
SQN-DC-V-ll.9, " Thermal Overload and Torque" 0310D (01/19/87)
TVA EMPLOYEE CONCERNS REPORT NUMBER:
213.3 (B)
SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 7 0F 15 None of the unidentified /unissued criteria listea above were committed to as required for restart in SQEP 29.
However, the titles of some of the unissued criteria imply that they may be safety-related, and portions of the unidentified criteria may have plant safety significance (e.g., emergency lighting sufficient to allow safe shutdown of the plant).
Per TVA memo ( App. A, 5.o; 08/11/86), Phase I of the DBVP (the l
completion of design criteria required for restart) is essentially complete; however, the areas identified above have not been addressed and not all C/Rs have been incorporated into the criteria required for restart.
To ensure that future licensing commitments are incorporated into design criteria, NEP 2.1 R0 ( App. A, 5.j ; 07/01/86) " Licensing l
Support" provides for coordination between licensing and engineering, and NEP 6.1 R0 ( App. A, 5.p, 07/01/86)" Change Control" provides for the revision of design criteria. This issue is addressed in Sequoyah Element Report 201.1 " Regulatory Requirements."
Findings:
a.
Review of a sample of the electrical design criteria indicates that standards, guides, and regulations are part of these criteria and are committed to when appropriate.
b.
Although this review indicates that most of the electrical design criteria documents currently exist, design criteria documents for the following could not be identified:
communications, overall plant security, instrumentation and controls, and lighting.
Additionally, it was determined that some design criteria were identified by TVA but never issued.
c c.
Review of C/R data sheets indicates that some commitments l
have not yet been incorporated into the electrical design l
criteria required for restart and that no plans for closecut l
of unincorporated C/R data sheets currently exist, as TVA has
" essentially completed" the DBDP.
d.
Provisions for the issuance or revision of electrical design criteria necessary to fully document the design bases (nonrestart portion) have not been made. Procedures for the closeout of nonrestart C/R data sheets have not been t
formulated.
l 0310D (01/19/87)
TVA EMPLOYEE CONCERNS REPORT NUMBER:
213.3 (B)
SPECIAL PROGRAM REVISION NUMBER:
1 PAGE 8 0F 15
==
Conclusion:==
The issues of the concern for the adequacy and existence of formal design criteria documents are valid.
Ibwever, the Design Basis Program has been implemented by TVA to correct the problem.
This program commits to the issuance of a minimum set of design criteria prior to restart, however, additional criteria may be necessary to fully document the design basis of the plant.
Although none of the identified unissued criteria is listed in SQEP-29 as required prior to restart, a review of the need for any of these criteria prior to restart, from a plant safety standpoint, is required.
Efforts to establish that all SON commitments are covered in design criteria are still nceded.
10.
CORRECTIVE ACTION:
The corrective action plans received via TCAB-044 and TCAB-057 on 12/30/86 and 01/15/87 respectively ( App. A, 5.s), respond to three general categories of problems as identified by CATDs 213.3-SQN-01,
-02 and -03.
The three general issues are:
nonexistence of criteria for some systems / subjects, criteria having been identified but never issued, and the status of the C/R tracking program.
Each plan addresses the specific points described on the CATDs for each of the general categories.
a.
With regard to the nonexistence of design criteria, CATD 213.3-SQN-01 identifies these subjects / system as not having formal design criteria documents instrumentation and controls (18C), lighting, communications, and overall plant security.
The disposition of each of these as stated in the corrective action shall be discussed separately.
o TVA acknowledges the need for general I&C design criteria and has committed to their issue before 09/30/87, which is after restart of Unit 2.
Al though portions of 18C are safety-related, TVA justifies the delay in issuance of these criteria until after restart by the following:
Requirements for the 18C portions of individual systems exist in the system's design criteria Set point adequacy has been evaluated through EQ and/or calculation programs required for restart i
03100 (01/19/87)
TVA EMPLOYEE CONCERNS REPORT NUMBER:
213.3 (B)
SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 9 0F 15 Requirements for instrument sense lines, although fragmented, do exist. Design criteria specifically for instruments sense line will be issued 03/87 (prerestart)
All ECNs and CAQs have been reviewed for impact on the safety portion of 18C as part of the restart effort No major I&C changes are now being, nor will be, made prior to issuance of design criteria o
The lighting criteria are to be issued 12/31/87.
The basis for the postponement of the issuance until after restart is the various tests (i.e., pre-op, start-up) and evaluations which have been performed over the years, and the fact that most emergency lighting system components are covered in other design criteria and on design drawings. Additionally, no major changes have been made, or are planned which would invalidate the previous tests and evaluations.
o TVA has committed to issue Communications Design Criteria by 12/15/87.
Since SQN communication systems are not safety-related, this criteria document is not required for restart by SQEP 29.
However, the portions of the communication systems which are important to safety (emergency operations, fire brigade, security) are covered in other safety-related design criteria and other design output documents.
o TVA has indicated that sufficient design criteria for l
plant security exist in the form of two design criteria:
SON-DC-V-23.0, " Security - Power Block;"
SQN-DC-V-23.1, " Electrical Security and Communication Equipment - Power Block Project." Because of the L
sensitivity of safeguard information, the evaluation team was not able to personally review these documents; however, through discussions with TVA (01/11/87, App.
I I
A, 7.d) it was established that these c'riteria contain sufficient detail for, and are applicable to, overall 4
plant security.
In addition, the SQN Physical Security Plan defines all aspects of the overall plant security including those in the above referenced design 1
c riteria. For these reasons, no additional security t
design criteria are required.
0210D (01/19/87)
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TVA EMPLOYEE CONCERN $
REPORT NUMBER:
213.3 (B)
SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 10 0F 15 1
b.
The second general problem, as identified by CATD 213.03-SQN-02, is that criteria have been identified but never issued.
The CATD lists these specific criteria:
o SQN-DC-V-9.7, "Erergency Cperations Facility" o
SQN-DC-V-9. ll,
" Safety Related Display Instrumentation" o
SON-DC-V-10. 6, "The Emergency Fire Protection 1
Communications Systems" o
SCN-DC-V-ll. 9, "Themal Overload and Torque" The disposition of each of these criteria is as follows:
o Design Criterion SQN-DC-V-9.7 is no longer required as TVA implemented a central emergency control center (CECC), located in Chattanooga, to satisfy the post-TMI NUREG 0696 requirements. DNE indicated ( App. A, 7.d) that the design requirements for the CECC are the responsibility of the Office of Nuclear Power and not project specific.
The specific requirements and interfaces with SQN site are identified in the SQN Radiological Emergency Plan.
This plan was reviewed in part by the evaluation team which substantiated DhE statements.
This design criteria number is to be deleted from the design criteria manual's index.
o The design criteria for the " safety-related display instrumentation," SQN-DC-V-9.11, have been incorporated into the post accident monitoring (PAM) design criteria, SQN-DC-V-19.0, via a design input memorandum and will be included in the next formal revision of I
that criterion. Therefore, a separate design criterion is not required and design criterion number SQN-DC-V-9.ll shall be deleted.
o The communication systems are currently outlined in the SQN FSAR (App. A, 5.t).
Included in the FSAR is a communication systems evaluation which indicates availability of adequate communication equipment during several postulated events (including fires).
TVA has indicated that the design criteria for the emergency fire protection comunication system will be part of the radio system design criteria which will be issued in conjunction with the communication design criteria.
l A separate criterion is not needed; therefore, the
~
number SQN-DC-V-10.6 will be deleted from the index.
All SQN communication systems are designated as nonsafety-related and, therefore, design criteria are not required to be completed prior to restart.
0?l00 (01/19/87)
= _ _ _. _ _ _ _ _
TVA EMPLOYEE CONCERNS REPORT NUMBER:
213.3 (B)
SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 110F 15 4
o Finally criterion SQN-DC-V-11.9, " Thermal Overload and Torque" is currently being developed and will be issued prior to restart.
c.
Lastly, the general issue of C/R close-out, as identified on CATD 213.03-SQN-03, has been resolved by the commitment by TVA to incorporate, or justify not incorporating, the remaining C/R data sheets.
Additionally, SQEP 18, which established the C/R tracking system, will be revised to make this an ongoing effort to ensure that design criteria will be kept up to date with regard to upper-tier document commitments and requirements.
The evaluation team concurs with these justifications and finds the actions to be sufficient to eliminate the described problems of the CATDs.
i 03100 (01/19/87)
TVA EMPLOYEE CONCERNS REPORT NUMBER:
213.3 (B)
SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 12 0F 15 APPENDIX A 5.
DOCUMENTS REVIEWED RELATED TO THE ELEMENT:
a.
SNP FSAR Chapters 7, 8, and 9 b.
Revised Sequoyah Nuclear Performance Plan, Volume II, Final Concurrence, (07/14/56) c.
Gilbert / Commonwealth Report No. 2614, "SQN Modifications for TVA," (03/0/386) d.
TVA memo from W. C. Drotleff to Those Listed, " Transition from OEP to NEP," (805 860410 008), (04/10/86) e.
Letter from B. J. Youngblood, NRC, to S. A. White, TVA, (06/23/86), with the Attached Transcript of the Investigative l
Interview Conducted by the NRC of 02/21/86 at the First Tennessee Bank Building in Knoxville, Tennessee f.
Nuclear Engineering Procedure 3.2, R0, " Design Input,"
(07/01/86) g.
Office of Engineering Procedure OEP-06, R0, " Design Input,"
(04/26/86) h.
Engineering Procedure EN DES-EP 3.01, R6, " Design Criteria,"
(05/22/84) 1.
Design Baseline and Verification Program, Sequoyah Nuclear Plant, R0, (05/01/86) j.
Nuclear Engineering Procedure 2.1, R0, " Licensing Support,"
(07/01/86)
I k.
SQN Design Criteria:
SQN-DC-Y-ll.2, R3 "125-V Vital Battery System,'"
(07/11/86)
SON-DC-V-ll.2.1, R2 "125-V Fifth Vital Battery System," (07/11/86) i SON-DC-V-ll.4 & 11. 5, R1
" Emergency Auxiliary Ac Power System, ' (07/25/86)
SON-DC-V-ll.4.1, R2
" Normal and Emergency Ac Auxiliary Pos.er System," (07/22/86) 1 f
1 N100 (01/19/87)
~
TVA EMPLOYEE CONCERNS REPORT NUMBER:
213.3 (B)
SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 13 0F 15 APPENDIX A (cont'd)
SON-DC-V-11.6, R3 "120-Y Ac Vital Instrument Power System," (07/11/86)
SON-DC-V-11.8, R0
" Diesel Generator and Auxiliary Systems," (07/10/86)
SON-DC-V-12.2, R6
" Separation of Electric Equipment and Wiring," (09/30/85) 1.
TVA memo from W. C. Drotleff to Those Listed, " Design Basis Program for TVA Nuclear Plant," (B44 860402 007), (04/08/86) m.
TVA memo from D. W. Wilson to Those Listed, "Sequoyah Nuclear Plant - Design Basis Effort to Support Restart,"
(B25 860409 009), (04/09/86) n.
TVA memo from W. S. Raughley to Those Listed, "Sequoyah Nuclear Plant Design Criteria," (08/01/86) o.
TVA memo from J. F. Cox to M. T. Tormey, "Sequoyah Design Basis Program to Support Restart," (B25 860811 100),
(08/11/86) p.
Nuclear Engineering Procedure 6.1, R0, " Change Control,"
(07/01/86) q.
Quality Assurance Procedure SQN-QAP-III-1.1, R2, " Preparation and Review of Design Criteria for Sequoyah Nuclear Plant,"
(04/07/71) r.
All documents listed in Section 6.
s.
Corrective Action Plan transmitted via TCAB-G44 (12/30/86) and TCAB-057 (01/15/87) t.
SNP FSAR Chapter 9, Section9.5.2.4 and Figure 9.5.2-3 6.
WHAT REGULATIONS, LICENSING COMMITMENTS, DESIGN REQUIREMENTS OR OTHER APPLY OR CONTROL IN THIS AREA?
Regulatory Guide 1.64 ( ANSI N45.2.11-1974), " Quality a.
Requirements for the Design of Nuclear Power Plant" 03100 (01/19/87)
TVA EMPLOYEE CONCERNS REPORT NlMBER: 213.3 (B)
SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 14 0F 15 APPENDIX A (cont'd) b.
10CFR50 Appendix B, Criterion II, " Design Control";
+
Criterion V, " Instructions, Procedures and Drawings,"
(06/26/71)
Nuclear Engineering Procedure (NEP) 3.2 R0, " Design Input,"
c.
(07/01/86) d.
Sequoyah Engineering Procedure (SQEP) 29 R1, " Procedure for Preparing the Design Basis Document for Sequoyah Nuclear i
Plant," (07/18/86) 7.
LIST REQUESTS FOR INFORMATION, MEETINGS, TELEPHONE CALLS, AND OTHER DISCUSSIONS RELATED TO ELEMENT.
a.
P. Nesbitt, J. Staub, TVA, I. Don-Doncow, Bechtel, meeting at SON site, ICM 530,(00/20/06)
I b.
Telecenforence between T. Sarver, I. Don-Doncow, Bechtel, and I
P. Nesbitt, TVA, IOM 542, (10/15/86) c.
Teleconference between T. Sarver, I. Don-Doncow, Bechtel, and P. Nesbitt, TVA, IOM 543, (10/21/86)
I d.
Teleconference between T. Sarver, Bechtel, and L. Ackley, P. Nesbitt, TVA, IOM 535, (01/12/87) 0?100 (01/19/87)
.,7 3
TVA EMPLOYEE CONCERNS REPORT NUMBER:. 213.3 (B) 2 SPECIAL PROGRAMi
.3 REVISION NUMBER: 1 PAGE 15 0F 15 CATD LIST The following CATDs identify ana provide corrective actions for the findings included in this report:
213.03-SQN-1 (01/09/87) (CAP revised 01/14/87) 213.03-SON-2 (01/09/87) (CAP' revised 01/14/87) 213.03-SCN-3 (01/09/87) (CAP revised 01/14/87) w i
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til REFEREllCE
- ECPS120J-ECPS121C TENNESSEE VALLEY AUTHORITY PAGE 80 FREQUENCY
- REQUEST OFFICE OF HUCLEAR POWER RUN TIME - 12:57:19 ONP - ISSS - RUM EMPLOYEE CONCERIl PROGRAM SYSTEM (ECPS)
RUN DATE - 12/02/86 I
LIST.0F EMPLOYEE CONCERN INFORMATI0tl CATEGORY: EN DES PROCESS 8 OUTPUT SUBCATEGORY: 21303 IllADEQUATE ELECTRICAL DESIGN CRITERIA KEYHORD A I
S GENERIC H
APPL QTC/NSRS P
KEYHORD B CONCERN SUB R PLT BBSH INVESTIGATION S
CONCERN KEYHORD C HUMBER CAT CAT D LOC FLQB REPORT R
DESCRIPTION KEYWORD D
-)
UI 100-019 EN 201u3 S HBN YYYY SR ELECTRICAL STANDARDS AND GUIDES ARE STANDARDS T50212 EN 20104 REPORT TREATED AS GUIDES, AND ARE NOT INCOR DESIGil RELATED EN 21303 P0 RATED IN DESIGN CRITERIA REQUIREME ELECTRICAL ilTS. ELECTRICAL DESIGN CRITERIA HH GENERAL ERE IT EXISTS, IS NOT COMPLETE, IS V AGUE, AND IN GENERAL IS INADEQUATE.
CI HAS NO FURTHER INFORMATI0tl. ANO NYMOUS CONCERN VIA LETTER.
1 C0tiCERNS FOR CATEGORY EN SUBCATEGORY 21303
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