ML20236E237
| ML20236E237 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/20/1987 |
| From: | Walters R, Zwisky D TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20236E191 | List: |
| References | |
| 201.4(B)-01, 201.4(B)-1, 201.4(B)-R, 201.4(B)-R00, NUDOCS 8710290136 | |
| Download: ML20236E237 (32) | |
Text
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' TVA EMPLOYEE CONCERNS REPORT NUMBER:
201.4 (8)
SPECIAL PROGRAM p
REPORT TYPE:
SEQUOYAH ELEMENT REVISION NUMBER: 0 r
i TITLE:
INCORPORATION OF REQUIREMENTS AND COMMITMENTS IN DESIGN i
Standards and Guides PAGE 1 0F 24 i
REX 56R FOR REVISION:
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PREPARATION i
PREPARED BY:
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SIGNATURE CONCURRENCES 70!P/
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8710290136 071023 PDR ADOCK 05000327.-
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DATE SIGNATURE DATE SIGNATURE 1
APPROVED BY:
ECSP MANAGER DATE MANAGER OF NUCLEAR POWER DATE CONCURRENCE (FINAL REPORT ONLY)
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' TVA' EMPLOYEE CONCERNS:
REPORTINUMBER: _201'.4 ' ( B ) -
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-SPECIAL PROGRAM
' REVISION NUMBER:;LO-V h
PAGEL2 0F:24 h-
- 1.
CHARACTERIZATION OF ISSUES:
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.Iss'es:
u Concerns:'
WI-85'-l'0-019 -
a.
Electrical; and other Engineering _
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Electrical' Standards and
-Standards and guides are treated-as j
Guides.'are treated as' guides, guides only._(e.g., they are utilized-1 and are not incorporated in.-
onlywhen'designerswanttoLuse-them)
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design criteria requirements.
and are not incorporated <in Design j
Electrical. design criteria',
' Criteria as requirements on a q
where it exists, is not'.
mandatory basis, complete, is; vague, and in' general.is inadequate. CI b.
TVA Design Guides and Standards.
a has no further information.
are inadequate.in many areas.
Anonymous. concern via letter.
- ^
c.
There are misuses _of'TVA design l
WI-85-100-038 guides and standards, such as ap-1 Design / installation drawings plicable parts. are not referenced' l
do not : always. represent = or or excerpted as requirements.
include. design requirements.
j 1
Design guides / standards are
' d.-
Engineering changes TVA standards 4'
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utilized only when designers
_after the job is complete.
2 want'to use them.-_ Design
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guides / standards are inadequate If TVA electrical procedures do.not
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in many ar.eas, and there are include IEEE standard requirements or misuses, such as applicable their equivalent, numerous problems j
partstare not referen'ced or-can result.- (This' issue is.also excerpted-as requirements.. CI addressed in Sequoyah Element 9
[
has.no further information.
Report 213.4).
f Anonymous concern via letter.
NOTE:
The following issues from-h BNP-QCP-10.35-8.26-2 these concerns are addressed in-Engineering can'do a job within their standards, then they other reports as indicated:
i' change those standards after Electrical design criteria either the job is complete.
does not exist, or if it exists, is not complete, is vague, j
IN-86-259 X11 If TVA clectrical procedures and in general is inadequate j
3 do not include IEEE star.dards (addressed in Sequoyah Element requirements or their Report 201.3).
j equivalent, numerous problems Design / Installation drawings do not can result._ Construction always represent or include design Dept. concern.
CI has no further information.
No requirements (addressed in Sequoyah follow-up required.
Element Report 204.4).
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' TVA EMPLOYEE CONCERNS REPORT NUMBER:
201.4 (B)
SPECIAL PROGRAM REVISION NUMBER:
0 I
PAGE 3 0F 24 2.
HAVE ISSUES BEEN IDENTIFIED IN ANOTHER SYSTEMATIC ANALYSIS? YES X N0 o
Identified by TVA WBN NSRS Date November 14, 1985 TVA Nuclear Safety Review Staff Investigation Report No.
I-85-545-WBN, Industry Requirements in TVA Electrical Procedures o
Identified by_ TVA SQN GCTF' Date June 4. 1986 TVA SQN - Generic Concern Task Force Report GCC-19-65 "IEEE Standards Not Included in Electrical Procedures" 3.
DOCUMENT NOS., TAG NOS., LOCATIONS OR OTHER SPECIFIC DESCRIPTIVE IDENTIFICATIONS STATED IN ELEMENT:
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No specific identifications.
4 INTERVIEW FILES REVIEWED:
Expurgated files for WI-85-100, IN-86-259, and BNP-QCP-10.35-8-26-2 were reviewed, and no additional unreviewed information was found.
5.
DOCUMENTS REVIEWED RELATED TO THE ELEMENT:
See Appendix A.
6.
WHAT REGULATIONS, LICENSING COMMITMENTS, DESIGN REQUIREMENTS OR OTHER APPLY OR CONTROL IN THIS AREA?
See Appendix A.
7.
LIST REQUESTS FOR INFORMATION, MEETINGS, TELEPHONE CALLS, AND OTHER DISCUSSIONS RELATED TO ELEMENT.
1 See Appendix A.
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- TVA EMPLOYEE CONCERNS
-REPORT NUMBER:- 201.4 (B)
SPECIAL PROGRAM REVISION NUMBER:
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PAGE 4 0F 24 t
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8.
EVALUATION 30 CESS:
Reviewed availabirotranscripts of NRC investigative i (l/.[c, a.
interviews to gain additional information regarding the 4 concerns.
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f',I Reviewed Engineering procedures to determine how' standards s
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Evaluated if option ~for use of standards and guides is given J
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to designer.
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. Reviewed engineering procedures and their references to
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,T guides and standards and determined which requirements are to be included on the drawings.
Determihed whether current procedures cover these issue to e.
J pr'avent recurrence of problems.
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Established examples of drawings from each discipline to be
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reviewed against design requirements, and reviewed and 3
eva M u d drawings.
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beterojhed if these issues have been identified in any other qric4rwiew (i.e., TVA QA audit, INP0 findings, etc.)
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' Emlyed,0esign 9aseline and Verification Program for Sequojag plant to'see if program adequately addresses these 3
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issues.
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9.q DISCU$fE.3,, F (DINGS, AND CONCL SIONS:
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SQN QA Manual, through R12, constitutes engineering 12/7..
des >gn procedures in effect
' N' 09/73-Division of Engineering Design (EN DES) Engineering OE/85:
Procedures (EPs), in effect
% Topical Report TVA-TR75-1 A, initially issued 19/S-( \\ ')06/76:TV5commitstoRegulatoryGuide1.64,whichendorsed
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1 07720-l'l (y /16/87) lNx i, -
' TVA EMPLOYEE CONCERNS
-REPORT NUMBER:
201.4-(B)
SPECIAL PROGRAM REVISION NUMBER:
0
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PAGE 5 0F 24 09/27/80:
Operating License (0L) issued for SQN Unit 1
]
J 09/15/81:
Operating License (0L) issued for SQN Unit 2 j
04/09/85:
TVA Topical Report TVA-TR75-1A, R8, issued 06/85 -
Office of Engineering Procedures (0EPs) are in j
07/86:
effect; supersede EN DES EPs 08/85:
TVA voluntarily shut down SQN Units 1 and 2 because of questions about the environmental qualification of electrical equipment 09/85 to present:
Sequoyah Project Manual (SQEPs and SQEP-Als) in effect 09/23/85:
TVA receives employee concern IN-8G-259-X11 11/01/85:
- TVA presents Sequoyah Nuclear Performance Plan (Draft) and its Corporate Nuclear Performance Plan (initial issue) to NRC 12/07/85:
TVA receives employee concern WI-85-100-038 12/07/85:
TVA receives employee concern WI-85-100-019 L
02/01/86:
TVA Office of Nuclear Power Employee Cm.cern Special Program initiated 03/10/86:
TVA Corporate Nuclear Performance Plan (CNPP) Volume 1, R0, submitted to NRC 04/08/86:
Design Basis Program for TVA plants accepted and adopted (formal design basis document to be captured and maintained) 05/01/86:
Formal Design Baseline and Verification Program for Sequoyah, R0, issued 06/20/86:
TVA receives employee concern BNP QCP-10.35-8-26-2 06/23/86:
NRC forwards transcript of interview with concerned individual to TVA 07/14/86:
Sequoyah Nuclear Performance Plan (SQNPP), Volume 2 revised and issued as R1
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TVA' EMPLOYEE CONCERNS REPORT NUMBER:- 201 1 (B)
- M SPECIAL' PROGRAM REVISION NUMBERS 0:
HI PAGE 6 0F 24 07/86 to_
Nuclear-Engineering Procedures (NEPs) in effect; present:
supecsede OEPs Discussion:
9.1 BACKGROUND
The Sequoyah' plant design was begun in the. late 1960s when compliance with. regulatory requirements was not required to-be.well documented.. The majority.of the.SQN licensing commitments were made~ in the late 1960s and early 1970s, and' some'of the present' day regulatory requirements are not Sequoyah requirements.
It is not necessary.to. update the Sequoyah plant to include:all of:the new guidance published-by NRC, or new industry standards, unless there are' specific requirements or commitments to do so.
Sequoyah. is a two-unit nuclear power plant. Each of the two
. units employs a pressurized water' reactor (PWR) nuclear steam
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supply system (NSSS) with four coolant loops furnished by
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Westinghouse. Electric Corporation. The ' plant was designed, built, and operated by TVA.
TVA Engineering Quality Assurance program policy directives and_ Engineering implementation procedures for Sequoyah have stipulated requirements in compliance with the applicable regulatory criteria and are' equivalent to those used by other utilities in the nuclear power industry.
These concerns were originally raised at Watts Bar Nuclear Plant (WBN).
They are considered generically applicable to Sequoyah Nuclear Plant (SQN) since the organization and procedures that governed SQN design were essentially identical to WBN.
The issues, identified in this element refer to possible programmatic deficiencies in the engineering design process related to the proper application of TVA engineering standards and guides and IEEE standards, or their equivalent,
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to design documents.
9.2 APPLICABLE DOCUMENTS The evaluation team identified the following documents that contain procedures to control engineering at SQN from project inception to the present-
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201.4 (B)
SPECIAL PROGRAM REVISION NUMBER:
0 I
PAGE 7 0F 24 l
o.
SQN Quality Assurance Manual, through R12 (01/70-12/73)
EN DES Engineering Procedures (Red Book) (09/73-06/85) o Office of Engineering Procedures (0EPs) (06/85-06/86) 1 o
Nuclear Engineering Procedures (NEPs) (07/86 to presOnt) o Sequoyah Project Manual (SQEPs) (09/85 to present) o 9.3 USE OF DESIGN STANDARDS AND GUIDES (Issues a, b, and c)
The following is a TVA statement of policy, taken from a TVA-memo (App. A, 5.nn), dated May 2, 1977, regarding their H
. Division of Engineering Design Manual.
"This manual contains EN DES-developed and EN DES-approved design guides and design standards for use within TVA's Division of Engineering Design.
EN DES design guides / standards provide tried and proven design approaches for solving design / construction problems
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commonly encountered on various TVA project.
j "The use of design guides / standards helps reduce i
overall expenditures of manpower, equipment, and material costs while promoting a higher level of confidence in our design processes. Therefore, EN DES design engineers will utilize design guides / standards in accordance with the following criteria:
"1.
Design Guides As the name implies, design guides include acceptable methods a designer may employ in solving design problems and for arriving at design solutions. Design guides must be considered, but the designer retains the option as to their use; e.g., he may use them for direct application, as examples only, or as reference sourCOs.
"2.
Design Standards Design standards represent this division's consensus that instruction /information contained in these documents will lead to safe, economical, and reliable designs.
Therefore, design engineers will refer to and when applicable will utilize the EN DES design
-k standards contained within the manual.
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SPECIAL PROGRAM-REVISION NUMBER: 0 f
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PAGE 8 0F 24 l
I In the event an approved design standard cannot be used
'for either technical or other valid reasons, the.
enginecr's group head is responsible for preparing a memo.to the EN DES Standards Board Chairman outlining the reason the design standard was not followed and the-design methods or approach used.in its place. This information,will enable the EN DES Standards Board to determine the need for revising the existing standard, reissuing a new standard, or reclassifying the design standard to a design guide."
The above stated policy is reflected in TVA procedures EN DES-EP 4.12, OEP-6, and the current NEP-3.2.
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Discipline Design Standards and Guides were distributed in approximately 1975. There are at least eleven volumes containing over 270 standards and guides. There are also.
four volumes of Standard drawings containing over 170 standard drawings.
These documents form the basis of engineering design performed before 06/85. The degree or 1
extent of implementation of each individual guide or standard is generally defined in the General, Purpose or Scope section-l
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of each document, using phrases such as, "this document provides instructions on how to design...; describes the.use l
L of...; provides the method of...; defines the method for designing...; is to be used by the designer..." etc.
The issue of inadequacies of standards nd guides was reviewed in discussions with evaluation team individuals of the various disciplines. Some inadequacies of TVA standards i
and guides were identified in Sequoyah Element Reports 237.2
( App. A, 5.uu), 238.1 ( App. A, 5.vv), and 240.0 ( App. A, 5.ww).
For example, in Sequoyah Element Report 237.2, Design Guide DG-E2.3.5 was found to be inadequate in that for motors 2 horsepower and smaller, there was insufficient criteria or guidance on interpretation of the National Electric Code (NEC) regarding setting of f ault protection at 1300 percent of full load.
In Sequoyah Element Report 238.1, the maximum allowable conduit fill indicated that Electrical Design Standard DS-E13.1.4 is not in agreement with FSAR and Design Criteria l
SQN-DC-V-11.3 requirements.
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SPECIAL PROGRAM j
REVISION NUMBER:
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PAGE 9 0F 24 Another example in Sequoyah Element Report 240.0(B) is that originally issued Design _ Standards DS-E12.1.1, E12.1.2, i
E12.1.3, and E.12.1.4 did not furnish the definition and information necessary for proper application of the ampacity-tables.
It should be noted that in each case of inadequacy found, corrective actions have already been addressed.
A TVA Standards Planning and Review Counc'il (App. A, 5.xx),
for the Electrical Engineering Branch (EEB) only, consisting 1
of senior experienced personnel, was established to review all electrical Design Guides and Design Standards and recommend. deletions, addition, and revisions.- This program is currently on hold and has been replaced by an EEB Design Control Process program as described in a TVA' memo (App. A, 5.aa).
Per previous discussion with EEB personnel (App. A, 7.a), this new program contains provisions for addressing
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design guides and design standards and will be completely implemented within two years.
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Discipline Standards and Design Guides for ~other branches are reviewed and updated on an ongoing basis by the individual 1
branches ( App. A, 7.b).
Twenty-two.available TVA SQN drawings ( App. A, 5.rr) were reviewed to evaluate the issue that design guides and design standards are not referenced or excerpted as requirements on drawings.
In only one of the twenty-two drawings was there found to be a design standard'directly referenced on a drawing. A more common practice is to-reference design criteria and construction specifications on the drawings.
In turn, the design criteria and construction specifications reference design standards and guides. Thus, design guides and standards are not normally referenced directly on drawings.
The allegation that engineering design guides are treated as guides, is a factual statement. Procedures allow engineers who use the guides to determine the extent to which the i
guides are used.
The treatment of TVA standards as guides is a violation of TVA procedures.
In view of the lack of any specifics to examine, this issue cannot be substantiated. Lack of conpliance with procedures, as implied on page 122 of the transcript of NRC investigative interview ( App. A, 5.w), was j
discovered by TVA Quality Assurance as part of their surveillance program.
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PAGE 10 0F 24
'The'TVA Top'ical Report TVA-TR75-1A, which is identified in the TVA Nuclear Quality Assurance Manual and the Sequoyah FSAR, states the following in subsection 17.1.3, " Design Control,"
" Design control measures for the. selection of suitable materials, parts, equipment, and processes are provided through the use of TVA design guides, standards, and specifications, and industry standards and specifications.
Requirements of these standards and specifications are assembled, interpreted and amplified in design
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criteria which are design input documents j
subsequently issued as early in the plant design as needed to provide a consistent basis.for naking design decisions, for establishing design l
verification measures, and for evaluating design changes."
To determine if standards and guides were to be incorporated in design criteria, EN DES-EP 4.12 on Design Guides and
[..
-Design Standards was reviewed. Also EN DES-EP 3.01 on design criteria documents was reviewed. Section 4.0.h, of EP 3.01 f
states:
" References--There are three types of references that are used in design criteria:
4 (1)
References.that are used specifically as design input. Typically, these are references to codes, guides, and standards, j
and the reference must specify the issuing organization, code, guide, or standard number, title, draf t, issue, or addendum date.
If sections of the reference do not apply, then either:
o Cite the applicable sections, or List the sections which are not being j
o referenced."
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The following is a quote from the current NEP-3.2.
i "The generic upper tier design input documents may include such things as the TVA Topical Report, design j
l-guides and standards, or NRC regulatory guides. The l
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TVA EMPLOYEE CONCERNS REPORT NUMBER:' 201.'4 (B)
SPECIAL PROGRAM REVISION NUMBER:c 0 i
b PAGE 11 0F 24 plant-specific' design criteria may be either design.
1 criteria that have been revised to capture these commitments or new design criteria documents."
l From a procedural standpoint design standards are to be
-incorporated into design criteria whenever they apply..
Design guides are incorporated.into' design criteria as j
determined by the individual design-engineer.
1 The evaluation team reviewed a sample of twelve (total) l (App. A, 5;qq) Mechanical,- Electrical,- and Civil Design '
Criteria documents to check the application of discipline design' standards and guides. The review revealedithat'the' C
design cr.iteria generally do incorporate references to appropriate standards and guides.
Also,'Sequoyah Element R.eport 213.3 provides the rusults of a review conducted to determine if Electrical Standards and Guides have been incorporated into design criteria requirements. This report finds that standards and guides-
- are,a part of.. design criteria and are committed.to when.
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appropriate.
Therefore, design standards and design guides both.from programmatic standpoint as well as applications standpoint are incorporated in SQN Design Criteria.
It should also be noted that the Division of_ Nuclear Engineering (DNE) is presently reevaluating the adequacy of SQN Design Criteria under the Design Basis Program and the Design Baseline and Verif.ication Program (App. A, 5.u and 5.v respectively).
9.4 CHANGING 0F ENGINEERING STANDARDS (Issue d)
EN DES-EP 4.12, which is a superseded procedure, under
" Policy" section 3.0, subsections 3.8 and 3.9, states:
"3.8 Deviation--If an approved design standard cannot be used for any VALID reason, a memo explaining the deviation must be sent to the EN DES Standards Board Chairman for subsequent evaluation by the original sponsoring branch or design project as a potential change.
"3.9 Deviation--If a revision to an EN DES DG/DS LDesign Guide / Design Standard] is needed to correct a significant or recurring condition which could result in a required nuclear
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safety-related function not being fulfilled, a 0772D-15 (04/16/87)
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.SPECIAL PROGRAM REVISION NUMBER: 0
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-nonconformance report'(form TVA 10700) must be processed as directed.in EN DES-EP l.26.- This
- excludes changes ;for. preplanned design development,. improvement of-satisfactory design,-
changes directed by standards or regulations, Land nonsafety-related. changes."
~ 0EP-6 and the current procedure NEP-3.2, state:
"Any deviation from the standard design'will be handled i
as a deviation'to this procedure."
'It is apparent that standards are changed:asethe'need arisesM
.and thatithere.is, and has been, a mechanism in place for:-
such changes. Changes generally are a way of upgrading the.
standards as experience dictates the need for a revision..-
9.5' -INCLUDING STANDARDS IN PROCEDURES ~(Issue e)-
The' issue that Electrical and other TVA Engineering Branch procedures do not.always. include. industry standards (e.g..
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-IEEE, ANSI) requirements is valid.in that it ii~a' factual-
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statement. This'is not considered a problem because industry standards.are included in other more appropriate design documents, such as design criteria and construction specifications.
Sequoyah Element Report 213.4 addresses the NSRS Report i
I-85-545-WBN and the GCTF Report GCC-19-65 in discussion of
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f this issue. Conclusions from these three reports are that the requirement of IEEE standards were found to'be incorporated properly in electrical design documents, consequently the issue that numerous problems could result was not considered valid.
Findings:
a.
Use of Design Guides and Standards:
o There are many design guides and design standards, including standard drawings, at TVA.
The use of design guides is optional to designers as o
defined in TVA procedures.
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PAGE 13 0F 24 The optional use of design standards is not permitted o
by TVA procedure. Design standards must be used where applicable, Treatment of Engineering standards as guides is not in o
compliance with TVA procedures.
b.
A few cases of inadequate TVA design standards and guides, which apply to all TVA nuclear plants, were noted in Sequoyah Element Reports 237.2, 238.1, and 240.0. Corrective actions are provided-in the noted documents. No examples of misuse were found, Design guides and standards are indirectly referenced on c.
drawings by means of references to design criteria or general construction specifications. The criteria and specifications contain references to the appropriate guides and standards, d.
Engineering changes to TVA standards after the job is complete are allowed by TVA procedure, and changes occur as they are needed and justified. Providing needed changes to
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design standards is considered a common practice.
Electrical and other TVA Engineering Branch procedures do not 1
e.
usually include industry standards (e.g., IEEE, ANSI) requirements. However, there are exceptions for specific reasons. Usually, industry standards are included in other more appropriate design documents such as design criteria and construction specifications. Further discussion related to IEEE standards in particular can be found in Sequoyah Element Report 213.4.
f.
As an additional finding, the evaluation team, in Section 9.3 of this report, cited the formation of an EEB Design Control Process program to review all electrical design guides and design standards and recommend deletions, additions, and revisions. This program has not yet been fully implemented.
==
Conclusions:==
The four specific concerns addressed by this report have been characterized into five specific issues (Section 1). The issues reflect the scope and technical aspects of the concerns and each issue is worded to bring a particular point into focus.
With the exception of the additional finding, the conclusions listed below address the issues raised in Section 1.
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The issue that design guides and standards are inadequate and misused was substantiated in a few cases. Corrective actions.
initiated through various other Sequoyah Element Reports should resolve this issue.
-The issue that design guides are optional to designers is valid, in i
that it is a factual statement. -However, it does not constitute a l
problem because TVA procedures, which are consistent with industry practice, allow the option.
The issue that design standards are optional to designers is not valid. TVA procedures require the use of design standards where they are applicable, subject to a mandatory documentation
.l' requirement for any deviation.
The issue that design standards and guides'are not referenced or excerpted as requirements on drawings is not valid. Some drawings do reference design standards. Standards are also referenced on drawings, usually indirectly, by way of references to the construction specifications and design criteria that address the appropriate standards and guides.
a
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The issue that Engineering changes TVA standards after the job is complete is valid. This is not considered a problem because it is-permissible by procedure and it is prudent to make changes when they are justified.
The issue that Electrical and other TVA Engineering Branch procedures do not always include industry standards (e.g., IEEE) requirements is valid in that it is a factual statement. This'is i
not considered a problem because industry standards are included in l
other more appropriate design documents, such as design criteria and construction specifications.
Additional Finding "f" noted that the EEB Design Control Process programs to review, and update as needed, all electrical standards and guides has not yet been completed. This program should be appropriately scheduled and completed.
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PAGE 15 0F 24 aq ti APPENDIX A l
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i 5.
DOCUMENTS REVIEWED RELATED TO THE ELEMENT:
a.
Title 10 of.the Code of Federal Regulations; Part 50
-(10CFR50), Chapter 1,- Appendix B,'" Quality Assurance Criteria
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For Nuclear Power Plants and Fuel Reprocessing Plants" b.
ANSI N45.2.11-1974, " Quality Assurance Requirements for the H
Design of. Nuclear Power P1 ants" 1
Regulatory Guide 1.64, " Quality Assurance.Re'quirements for c.
the Design 'of Nuclear Power P1 ants," R2, (06/76).
I
.d.
ANSI:N45.2-1971, " Quality Assurance Program Requirements for Nuclear Power Plants"'
Regulatory Guide 1.28, " Quality Assurance Program e.
Requirements (Design and Construction)," R0,. (06/07/72) f.
ANSI N45.2.10-1973, " Quality Assurance Terms and Definitions" ANSI /ASME NQA-1, 1983 Edition, " Quality Assurance Program.
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Requirements for Nuclear Facilities" h.
Sequoyah Preliminary Safety Analysis Report, (PSAR) 1.
Sequoyah Final Safety Analysis Report (FSAR) Updated through Amendment 3, (04/86) j.
TVA-TR75-1A, " Quality Assurance Program Description for the Design, Construction, and Operation of TVA Nuclear Power Plants," R8, (04/09/85) i i
k.
Nuclear Quality Assurance Manual, (NQAM), (11/14/85) 1.
Nuclear Quality Assurance Manual (NQAM), (interim revision),
(10/21/86) 1-Sequoyah Nuclear Plant Quality Assurance Manual (SQN QAM) m.
Quality Assurance Procedures (QAPs) employed in the review of this element are from Revision 11 of the SQN QAM (and prior).
SQN-QAP-III-1.1, R2, " Preparation and Review of Design l
Criteria for Sequoyah Nuclear Plant," (04/07/71)
I I
l 0772D-14 (04/16/87) r
___m___._
_ __-__.__ M
J
,.e
'TVA~ EMPLOYEE-CONCERNS' REPORT NUMBER: 201.4 (B)
SPECIAL' PROGRAM.
REVISION NUMBER::'O-(h PAGE 16 0F 24-APPENDIX A (Cont'd) q l0ffice _of. Engineering Design and Construction (0EDC) Quality-n.
Assurance Manual (09/12/75) 1 4
.o..
- TVA Division.of-Engineering Design Engineering Procedures l
Manual Volume 1, Section 1.0, Category: ' General.
Volume 2, Section 3.0,' Category:
Engineering Volume 3, Section 4.0, Category: Design
" Design Criteria Documents -
LEP 3.01, R6 Preparation, Review, and Approval,
(05/22/84) 4 EP 4.12, R5 "EN DES Design. Guides and Designi Standards - Preparation, Review..
Approval, Distribution, and Revision,'"
(04/15/82)
I p.
TVA Office of. Engineering (OE) Procedures fianual-OEP-06, R0'
" Design Input," (04/26/85)
OEP-08, R0
" Design Output," (04/26/85)
OEP-10, R0-
" Review,"-(04/26/85) o q.
TVA Division Nuclear Engineering (DNE) Procedures Manual:
NEP-3.2, RO " Design Input," (07/01/86)
NEP-5.1, R0 " Design Output, (07/01/86)
NEP-5.2, R0 " Review," (07/01/86)
Sequoyah Nuclear Plant Design. Criteria Manual (6 Volumes),
r.
(06/26/86)
Gilbert / Commonwealth, Inc. Report No. 2600, " Assessment of s.
Design Control Program for the Sequoyah Nuclear Plant, Prepared for the Tennessee Valley Authority," (10/85)
(RFI 538) i t.
Gilbert / Commonwealth Inc. Report No. 2614, "Sequoyah Nuclear Plant Modification for Tennessee Valley Authority,"
(03/03/86) (RFI 538)
TVA memo from W. C. Drotleff, Jr., to Those Listed, u.
(R. G. Domer, et al.), " Design Basis Program for TVA Nuclear k
Plants," (B44 860402 007), (04/08/86) 07720-15 (04/16/87) c _ -_ _ ___ _ _ _
i
TVA EMPLOYEE CONCERNS REPORT NUMBER: 201.4 (B)
SPECIAL PROGRAM REVISION NUMBER: 0
(
PAGE 17 0F 24 APPENDIX A (Cont'd)
I v.
TVA memo from D. W. Wilson to Those Listed, (G. Aklu, et al.), "Sequoyah Nuclear Plant - Design Baseline and Verification Program," (B25 860506 020), (05/06/86) w.
Letter from B. J. Youngblood, NRC, to.S. A. White, TVA (B45 860714 832), with the attached transcript of the investigative interview conducted by the NRC on 02/21/86 at the First Tennessee Bank Building in Knoxville, TN (06/23/86) s x.
TVA memo from R. L. Gridley to Those Listed (H. L. Abercrombie, et al), "Sequoyah Nuclear Performance Plan - Volume II - Final Concurrence," (L44 860714 800),
(07/14/86) y.
TVA NPP, Volume 1, Corporate Nuclear Performance Plan, RO, (03/10/86) z.
TVA NPP, Volume 2, Sequoyah Nuclear Performance Plan, R1,
---[
(07/86) aa.
TVA memo from W. S. Raughley to Those Listed (J. D. Collins, et al), " Policy Memorandum PM 86-24 (EEB) - EEB Design Control Process," (843 861017 904), (10/17/86) bb.
TVA memo from J. F. Cox to M. T. Tormay, "Sequoyah Design Basis Program to Support Restart," (B25 860811 100),
(08/11/86) cc.
Letter from NRC to S. A. White, TVA, " Report Nos.
50-327/86-27 and 50-328/86-27," (A02 860502 002), (04/22/86) dd.
TVA memo from D. W. Wilson to H. L. Abercrombie and R. L.
Gridley, "Sequoyah Nuclear Plant (SQN) - NRC Inspection Report 50-327/86-27 and 50-328/86-27," (B25 860722 010),
(07/22/86) ee.
Letter from NRC to. S. A. White, TVA, " Report Nos. 50-327/86-38 and 50-328/86-38," (09/15/86) ff.
Letter from NRC to C. C. Mason, TVA, "Re Nos. 50-327/86-45 and 50-328/86-45," (10/ port 31/86) 99 TVA memo from L. L. Jackson to Those Listed (H. L. Abercrombie, et al), " Institute of Nuclear Power
(
Operations (INPO) Corporate Evaluation Responses" (A02 860813 012), (08/14/86) 0772D-15 (04/16/87)
i TVA EMPLOYEE CONCERNS REPORT NUMBER: 201.4.(B) j SPECIAL PROGRAM j
REVISION NUMBER: 0
(
PAGE 18 0F 24 APPENDIX A (Cont'd) i hh.
Letter from Impell to TVA (Attention: Mr. Henry Jones),
" Design Control Program External Audit Finding Evaluation,"
(Impell/TVA-86-162),(06/19/86) 11.
Letter from Impell to TVA (Attention: Mr. Henry Jones)',
l
" Design Control Program External Audit Finding Evaluation,"
(Impell/TVA-86-180), (06/30/86) jf.
Letter from Impell to TVA (Attention: Mr. Henry Jones),
" Design Control Program External Audit Finding Evaluation,"
i (Impell/TVA-86-197), (07/10/86) kk.
Letter from Impell to TVA (Attention: Mr. Henry Jones),
" Design Control Program External Audit Finding Evaluation,"
(Impell/TVA-86-233),(07/23/86) 11.
Report:
" Assessment of Engineering Design Control for the Browns Ferry Nuclear Plant," written by Myer Bender, F. E.
(.-
Laurent, E. H. Cole and R. D. Sabin, (09/85)
INP0 Report of Seouoyah Nuclear Plant TVA, February 1984 mm.
Evaluation TVA memo f' rom R. H. Dunham to Holders of Division of nn.
Engineering Design Design Manual, "EN DES Design Manual -
Statement of Policy," (no RIMS number), (05/02/77) oo.
TVA Division of Engineering Design Design Manual Architectural Volume 1 (07/18/84)
Civil Volume 1 (01/04/84)
Volume 2 (09/09/82)
Electrical Volume 1 (11/21/85)
Volume 2 (02/13/86)
Volume 3 (12/05/85)
Volume 4 (03/15/85)
Mechanical Volume 1 (07/15/85)
Volume 2 (04/03/85)
Volume 3 (04/03/85)
Volume 4 (12/18/85) k 07720-14 (04/16/87)
TVA EMPLOYEE CONCERNS REPORT NUMBER:
201.4 (B)
SPECIAL PROGRAM
'j REVISION NUMBER: 0
{
b PAGE 19 0F 24 1
j 1
APPENDIX A (Cont'd) pp.
TVA Division of Engineering Design Standard Drawing fianual Civil Volume 1-(07/22/85)-
Electrical Volume'1 (04/03/85) l' Volume 2 (09/05/84) j L
Volume 3 (01/03/86) l Mechanical Volume 1
.(09/07/82)_
qq.
SQN Design Criteria:
SQN-DC-V-1.3.2,R8 "fliscellaneous Steel Components for, j
l~
Class I Structures," (09/14/84)
SQN-DC-V-2.3, R0
" Containment Vessels," (07/01/69)
SQN-DC-V-2.16, R0
" Single Failure Criteria for Fluid and Electrical Safety-Related Systems,"
[.
(07/14/86)
SQN-DC-V-3.2, R 1 "The Classification of Heating',-
Ventilating and Air Conditioning Systems," (09/25/85) 1 j-SQN-DC-V-4.1.1,R0
" Main Steam System," (07/11/86)
SQN-DC-V-7.4, R2
" Essential Raw Cooling Water System (67)," (07/11/86) i SQN-DC-V-ll2, R3 "125-V Vital Battery System,"
)
(07/11/86)
SQN-DC-V-11.6, R3 "120-V Ac Vital Instrument Power System," (07/11/86) i I
SQN-DC-V-12.2, R6
" Separation of Electric Equipment and Wiring," (09/30/85)
SQN-DC-V-13.3, R3
" Detailed Analysis of Category I l
Piping Systems," (08/13/84) i SQN-DC-V-13.9.1, R0
" Diesel Generator Building Ventilation System - System 30-DGB," (07/11/86) k SQN-DC-V-26.2, R0
" Environmental Qualification to 10CFR50.49," (07/21/86) i 0772D-14 (04/16/87)
E_----_---_
g:'
-q 4
i p3,s TVA EMPLOYEE CONCERNS
REPORT NUMBER: 201.4 (B)
I
- SPECIAL PROGRAM f
REVISION NUMBER:.O
'PAGE 20 0F 24 APPENDIX A (Cont'd)-
.i tr..
45W880-26, R18
" Conduit and' Grounding Cable Trays-
- l H
Fire Stop Penetrations Det. Sh 13,"-
(04/11/77-(TTB'157)-
47W920-1, R40
" Powerhouse Control Building-tiechanical Heating, Ventilating and-Air Conditioning," () initial issue j
08/22/71), (TTB 159
~
47W920-2, R36
" Powerhouse Auxiliary Building
' Mechanical Heating, Ventilating and Air Conditioning," (_12/01/82),.
" Powerhouse Auxiliary Building tiechanical Heating,' Ventilating ~ and g(.,;
Air Conditioning,".(10/09/81,-(TTB 159) j 47W920-6, R32
" Powerhouse Auxiliary Building-tiechanica1' Heating, Ventilating and-i Air-Conditioning," '(09/10/82),
" Powerhouse Unit 1-2 Mechanica1L Sampling and Water Quality' System,"
(01/10/74) j 47W343-5, R1
" Powerhouse Units 1-2 liechanical 4
Sampling and Water Quality System,"
)
(02/25/74) j 1
i 47W809-2, R6
" Auxiliary Building Unit 1 and 2 Flow Diagram CVCS Chemical Control,"
(10/31/86) a 47W813-1, R27
" Powerhouse Units 1 and 2 Flow Diagram 1
Reactor Coolant System," (06/18/86) 47W815-1, R12
" Powerhouse Turbine Building Units 1 and 2, Flow Diagram Auxiliary Building System," (10/31/86) b 0772D-14 (04/16/87) i
f
\\
?:
!TIAEMPLOYEECONCERNS.
REPORT NUMBER: 201.4 (B) 3s A
- SPECIAL PROGRAM REVISION NUMBER
0-L PAGE 21 OF.24)
APPENDIX A (Cont'd)-
1 47W839-l'R9-
- " Diesel Generator Building Flow.
Diagram Diesel Starting Air System,
.(11/07/84)l 48N904,- R12
." Reactor Building Units 11 and 2 -
' Misc. Steel:- S.G., R.C.,' Pump.and
-Press. Rel.' Tank'
. Access' Platform Sh..
2" 48N905,:R24-l" Reactor Building Units 1;and 2 -
Misc.' Steel - S.G., R.;C. Pump and..
Press. Rel.:Tnk. - Access. Platform --
Sh..1," (date not legible) 48N906, R12
" Reactor Building Units 1.and 2 -
Misc. Steel - S. G., R.'C. Pump and i
Press. Rel. Tnk. - Access Platform 9
Sh. 2," (03/16/85) 48N908, R10
" Reactor Building Units 1 and 2 -
Misc., Steel - Steam Generator - Access-Platform," (04/21/81) 48N908-1, R7
" Reactor Bufiding. Units 1 and 2 -
Misc. Steel - Steam Generator - Access Platform," (11/29/85) 48N908-2, R6
" Reactor Building. Units 1 and 2 -
Misc. Steel - Steam Generator - Access Platform," (02/18/84) 48N908-3, R3
" Reactor Building Units 1 and 2 -
Misc. Steel - Steam Generator - Access Platform," (03/21/85) 48N908-4, R1
" Reactor Building Units 1 and 2 -
Misc. Steel - Steam Generator - Access Platform," (03/21/85) 48N908-6, R0
" Reactor Building Units 1 and 2 -
Misc. Steel - Steam Generator - Access Platform," (11/29/85) l[
/
0772D-14 (04/16/87)
=
____ _ _ - - _ =
1 TVA EMPLOYEE CONCERNS REPORT NUMBER:
201.4-(B)
SPECIAL PROGRAM-REVISION NUMBER: 0 PAGE 22 0F 24
]
APPENDIX A (Cont'd) 47W476 Series, R0
" Piping Bill of Material Sequoyah Nuclear Plant Units 1 and 2, Reactor Building - Annulus Floor DR and EMB-Piping," Sheets 1 and 2, (01/17/73) 47W476-1, R9-
" Powerhouse Reactor Building - Units.1 and 2, Mechanical Annulus Floor Drains and Embedded Piping," (07/02/81) ss.
TVA OE General Construction Specification No. G-3, (no..
rev.), " Installing Electrical Conduit Systems and Fabricated i
Conduit Boxes," (05/15/73) tt.
TVA OE General Construction Specification No. G-32, Rll,
" Bolt Anchors Set in Hardened Concrete," (B42 851216 500),
(01/31/CE)
Sequoyan Llement Report 237.2, R2, (01/13/87) uu.
vv.
Sequoyah Element Report 238.1, R2, (01/08/87)
Sequoyah Element Report 240.0, R1, (02/13/87) ww.
xx.
TVA memo from A. F. Pagano to Electrical Engineering Files, "EEB Standards Planning and Review Council Meeting,"'
[B43 860106 911], (01/03/86) 6.
WHATREGULATIONS,LICENSINGCOMMITMENTS,DESIGMEJUIREMENTSOROTHER APPLY OR CONTROL IN THIS AREA?
10CFR50, Appendix B, " Quality Assurance Criteria For Nuclear a..
Power Plants" b.
ANSI N45.2.ll-1974, " Quality Assurance Requirements for the Design of Nuclear Power Plants" Regulatory Guide 1.64, " Quality Assurance Requirements for c.
the Design of Nuclear Power Plants," R2, (06/76) d.
Sequoyah Final Safety Analysis Report (FSAR) Updated, through Amendment 3, (04/86) i 0772D-14 (04/16/87)
j y
4 T' ~
:.TVA EMPLOYEE CONCERNS REPORT NUMBER: 201.4.(B) i a
'SPECIAL' PROGRAM-0-
REVISION NUMBER:'
[
PAGE 23 0F'24' l
f.
APPENDIX A'(Cont'd)'-
[
TVA' Division of Nuclear Engineering,-Nuclear Engineering
' e.
Procedures-(NEPs):
' NEP-3.2, R0 " Design Input," (07/01/86)- and " Interim 0rder liemorandums"; (09/12/86), (.12/22/86), and (03/18/87)-
- NEP-5.1, R0 " Design ' Output,". (07/01/86)
.NEP-5.2, R0 " Review," (07/01/86)
- {
7.
LIST REQUESTS F'OR INFORMATION, MEETINGS, TELEPHONE CALLS, AND'OTHER-t
' DISCUSSIONS RELATED TO ELEENT.
l Trip Report, D. Zwicky personal visit to Knoxville, October a.
21-23,.1986,!and SQN Site, IOM 469,(10/24/86)'
b..
Telecon, D. 'Zwicky, Bechtel, with D. Popham,tBechtel and
.(c Terrell Clift, TVA IOM 580,-(01/27/87) c.
tRFI SQN-774, (01/28/87)
(
07720-14~(04/16/87)
o ;;.
- TVA EMPLOYEE CONCERNSL REPORT NUMBER:' 201.4-(8)-
h" - il '
SPECIAL PROGRAM REVISION NUMBER:
0-
~ PAGE 24 0F 24-CATD LIST L
The following CATD form is included as part of this report:
201 04 ~ NPS ;01- (Issue " f") -
The' above generic NPS (not plant-specific) CATD will be applicable to:
HOTE:
other TVA' plants.
I t '
i ll
- \\
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(
ECTG Corrective
.(
action Tracking Document
\\'
-(CATD)
.l INITIATION Applicable ECTG Report No.:
- 2. o I 04- ( B) 1.
Immediate Corret.tive Action Required:
O Yes
)( No l
2.
Stop Work Recommended:
O Yeii
)5[ No l
3.
CATD No. ~2.01 0 4 NPS o1 4.
INITIATION DATE 04/o8/67 I
5.
RESPONSIBLE ORGANIZATION:
DN E - Zwox viLLE 6.
PROBLEM DESCRIPTION: J( QR O NQR E E t$
D E S ic. N Co NT7o L P 2.o c.e 5 5 P e o ca eau
-ro 52.Erv 1 E W ALL E L E c f 2.) c_ A L 0 6'5 t c:m N <= V t O E 5 l
q A MO O E 9 c.,. M STANDAuoS ANO W. WC.o M M c N O i
-DELGTtoNs. A o o t T't o N S ANO REvtstoNs. uAS l
NOT M E"Y SEEN FULLN
l
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PREPARED BY:
NAME D "LW\\tKY F
W DATE: # /08 /17
)
8.
CONCURRENCE:
CEG-H h %ed /2#16W DATE:
4/ 2o-47 i
O DATE:
I 9.
APPROVAL:
ECTG PROG'fA'M MGR.
I CORRECTIVE ACTION
'10.
PROPOSED CORRECTIVE ACTION PLAN:
i j
O ATTACHMENTS 11.
PROPOSED BY:
DIRECTOR /MGR:
DATE:
12.
CONC'!RRENCE: CEG-H:
DATE:
ECTG PROGRAM MANAGER DATE:
VERIFICATION AND CLOSEOUT 13.
Approved corrective actions have been verified as satisfactorily implemented.
SIGNATURE TITLE DATE j
(
0686T 4
6..
t E*-
,. ;, a.,.,, o 3 <,,.... w
. 805-T25 870611 i
1
' tJ N n t:l! F I ATI 8 G Wl:MN.\\llW I.
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. TENNESSEE VALLEY AUTif 0I'ITY j
James L. McAnally, Correctiv' Action Program Manager, A108 108,
.' 70 '
e
. ONP, Watts'Bar Nuclear Plant L.
_LFROM W.'R. Brown, Jr,. Program Manager Employee Concerns Task Group..
-ONP, Watts Bar Nuclear Plant L
"^'"
JUN 111987
SUBJECT:
' SEQUOYAH NUCLEAR PIANT (SQN) - EMPLOYEE CONCERNS' TASK GROUP (ECTG)
ELEMENT REPORTS -- ENGINEERING CATEGORY - CONCURRENCE WITH CORRECTIVE l-
. ACTION PLAN (CAP)
.i
,'l
.g
.3 l'
l-The. category evaluation group leader, Engineering, concurs with the CAP presented in the attached report.
l Report'No.
Transmittal' RIMS-No.
l 201.04 T41 870608 887
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d'd W. R. Brown, Jr.
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Attachments cc.(Attachments):
1 RIMS,'MR 4N 72A-C-f Jack Howard, ECTG Bldg., ONP, Watts Bar Guy Huff, ECTG Bldg., ONP, Watts Bar-l I
G. R. McNutt. ECTG Bidr,., ONP, Watts Bar l
5418T 4
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1 s.6,
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f TV A 64 (C5 9 45)(Op WS $ 89) 1.
7060S 67
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!; nitro STATE 3'CoVERsatar 2_'CmOTondum TENNESSEE VALLEY AUTHORITY 1
{
W. R. Brown, Jr., Program Hanager, Employee Concerns Task Group.
TO Hatts Bar Nuclear Plant.ONP
' James' L. McAnally, Corrective Action Program Hanager, Hatts Bar FRCH' Nuclear Plant,0NP-DATE g.g g 7 l
HATTS BAR NUCLEAR PLANT (WBN) - TRANSMITTAL OF ECSP CORRECTIV i
SUBJECT:
ACTION TRACKING COCUMENT(S)
(CATO)
ECSP Fact Sheet Number: J20 / o -/
r ECSP CATD(s) Numbers
- 6:of o 4 - A ) As - n /
i
~
The above listed, completed CATO(s) are being returned according to f)..
your instructions.
i
[.'
ames L. McAnally JL}ic:NLC Attachments cc (Attachments):
,h',-
,6 /.
/
Er.nt = Cw..
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l e..... m e. 4w o i
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CNrrEli 8TATI.5 covi;t:N.sti:NT
/
i Memorandum TENNESSEE VALLEY AUTHOI:ITY
-l t
1 l
TO J. L. McAnally, Corrective Action Program Manager, WBN, ONP f
FROM
- Terry C. Price, DNE, 5-224 SB-K j
DATE.
- ' [f 7
7
SUBJECT:
WATTS BAR NUCLEAR PLANT (WBN) - TRANSMITTAL OF CORRECTIVE ACTION PLAN (CAP)
Report Number 4 O / /~> l[- A!/#;- () /
CAP Number (20 / C I- /Ll / 6 - O /
The attached proposed corrective action plan has been prepared as requested.
An advance copy of this CAP has been forwarded to (%w /'/ b /v' of Employee Concern Special Program (ECSP) for their information.
W4 T. C. Price 1
TCP:JN Attachment IO 6 Awy[ '
a) 2C / 2 G c -K l
1957P 1
s T'
3 m m,
.a.,m.
,.,,,m,, s gm..,, m, m,,
t i
ECTG Corrective Action Tracitine, Document (CATD)
INITIATION Applicable ECTG Report No.:
~2. O I 04-(B) 1.
Immediate Corrective Action Required:
O Yes
)( No 2.
Stop Vork Recor:: mended:
O Ye's
)3( No 3.
INITIATION DATE 0 4 / 0 B / e:~7 5.
RESPONSIBLE ORGANIZATION:
O N E - l( N o x v i L L E l
6.
PROBLEM DESCRIPTION: E QR O NQR EE6 DE S i C N C O ' N T* E.o L P 2 o C. E 5 5 PEoC=RAu
-T o c2 E'v \\ E w ALL E. L s c_ T 21 C AL 0 6 5 t Cm N GVtDE5 AND D E S \\ cm N ST A N O Au.o s ANO RWCcvMEND DELGtsoN%
A O O t"T t o N S ANO RE V \\ 5 t c N 3. uA5 NoT M E"T saf g g g pyyty gupugup,yrep, 3
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_ O ATTACHMENT,5 7.
PREPARED BY:
NAME D. Tw\\CKY F
W DATE: # /08 /79 8.
CONCURRENCE:
CEG-H h %m2 /2/hcW DATE:
4I. 2 0 -E 7 I
9.
APPRO7AL:
ECTG PROG $%M MGR. O &#EZ/u
/b DATE:
V/2247 CORRECTIVE ACTION P
PROPOSED CORRECTIVE ACTION PLAN:"
lO.
$EE ATT A cKh O ATTACHMENTS 11.
PROPOSED BY:
DIRECTOR /MGR:
- 59:
hm DATE:
12.
CONCURRENCE: CEG-H:
G R @M')J /A,.
DATE:
4,/ioh7 ECTG PROGRAM MANAGER DATE:
VERIFICATION AND CLOSE00T 13.
Approved corrective actions have been verified as satisfactorily iraplemented.
SIGNATURE TITLE DATE j
0686T r
u CATD NO.
20104-NPS-01 j
10.
PROPOSED CORRECTIVE ACTION PLAN r
A comprehensive review of TVA electrical design standards and design guides will be completed by 10/17/88, at which time a program for maintaining the integrity of the standards and guides will be in place.
Maintenance of the standards and guides will be an ongoing process.
Does the corrective action plan rely on or take credit for currently identified or previously completed work?
Yes X
No If yes list parent documents (e.g. NCR, SCR, CAR, Audit, etc.)
Polley memo PM86-24 (B43 861017 904)
Does the problem described constitute a condition adverse to quality (CAQ)?
Yes No X
If Yes CAQ No.
)
Schedule for completion of corrective action (schedule date, if know, or mileston (e.g. BFL1, etc.)
October 17 1988 j
b$bb
.$~ Y fl
!d :Aw LL hl
/sf.yy 11.
Prepared by/Dat'e Proposed 6y'/Date b$4/'
2161P 0c4]sM!ecf' @ C& l'
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j-Bechtel Western Power Corporation o
.g i' ' t Engineers - Conmuctors o
- -T,.9-3 N
F Fdty Beale Street San Francisco, Cahfornia 1
E '*
uasi Address: PO Boe 3965. San Francisco. CA 94M9
'i r.
i +=y,
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fj June 9, 1987 3
)
%3
.i v s
].
l' BLT-243 1,1 3
Mr. George R. McNutt Engineer,ing CEG-H w,
Tennessee Valley Authority 3
Knoxville, Tennessee 37902 1
Subject:
Watts Bar Nuclear Plant Employee Concerns Eialuation Program Tennessee Valley Authority Job Id.116985-026 CATO 20104 NPS OI; CAP CONCURRENCE i
^
Dear Mr. McNutt:
(
) In the CAP for CATO 20104 NPS 01 as transmitted by TCAB-095, TVA has committed l
, as follows.
"A compreherisive review of TVA electrical design standards and s,, p design guides will be completed by 10/17/88, at which time a program for maintaining the integrity of the standards and guidas will be in
),
, pl ace.. Maintenance of the standards and guides will be an ongoing T
/ proces4 "
[ '( \\ a
,1, v
The aforementioned CAP is acceptable to the Evaluation Team and will be i
k'
.I incorporated into the subcategory report.
" j'
\\ g-s g
~
.i Very truly yours, 1
/3 s
t
[<
I G. L. Parkinson Project Manager s
1 GLP/gd, t
25940 h
6/9/F7---GRM:RMW ec: RIMS, MR 4N 72A-C R. Denny, DSC-E SQN it. R. Brown, ECTC Bldg., Watts Bar ONP y
As I
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L*NITED STATES GOVEitNMENT J
. Memorandum TENNESSEE VALLEY AUTHOItITY l
TO W. R. Brown, Program Manager, Employee Concerns Task Group, ONP, Watts Bar Nuclear Plant FROM H. L. Abercrombie, Site Director, ONP, O&PS-4, Sequoyah Nuclear Plant December 11, 1986 DATE SUDJECT:
SEQUOYAH NUCLEAR PLANT (SQN) - EMPLOYEE CONCERNS TASK GROUP (ECTG) -
L ENGINEERING CATEGORY REPORTS - NONRESTART JUSTIFICATION CONCURRENCE
References:
1.
Your memorandum to me dated October 28, 1986,'" Watts Bar Nuclear Plant - Employee Concerns Task Group -
i Engineering Category Concerns - Review of Elements to Determine if They are Restart Items" (T25 861028 876) 2.
Your memorandum to me dated November 18, 1986, " Watts Bar Nuclear Plant - Employee Concerns Task Group -
Engineering Category Concerne - Review of Elements to Determine if They are Restart Items" (T25 861118 831) 3.
Your memorandum to me dated November 20, 1986, " Watts Bar Nuclear Plant - Employee Concerns Task Group -
{
Engineering Category Concerns - Review of Elements to Determine if They are Restart Items" (T25 861120 853)
In response to your requests (see above references), the following element report noncestart justifications have been reviewed.
I concur that these RECEIVED reqortsarenotrequiredforrestart:
.4
.4 232.8 g 77g imMc.c:
G/:W i'm1.u;a icAlbo, I cannot concur with the nonrestart justification for Element Report d E.,m.3p.5 as submittod (soe reference 1) because this report and associated 2
j{ } d _. 3 nTDs are currently under review for corrective action.
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