ML20214M911
| ML20214M911 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/18/1987 |
| From: | Martin M TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20214M914 | List: |
| References | |
| NUDOCS 8706010464 | |
| Download: ML20214M911 (9) | |
Text
--
W
' he t.
TENNESSEE VALLEY AUTHORITY-Watts Bar Nuclear Plant P.~0. Box 800 Spring' City, Tennessee 37381 May 18, 1987
~
U.S. Nuclear Regulatory Commission
-Attn: Document Control Desk Washington. DC - 20555 Gentlemen:
In the Natter of the Application of~
)
Docket Nos. 50-327 Tennessee Valley Authority
)
50-328 EMPLOYEE CONCERNS TASK GROUP (ECTG) provides a listing of the report numbers, the related employee concerns, and the previous submittal dates if applicable. To assist you in your review of these reports, Enclosure 2 provides a comparison between the ECTG Writer's Guide' recommended report format and the transmitted reports. transmits the revised final element reports.for 2 elements addressing Sequoyah Nuclear Plant employee concerns in the following categories:
Engineering
- 1 report Material Control - 1 report As indicated by the report cover sheets, these reports have completed final review by the Senior Review Panel and the Employee Concern Task Group management.
Please telephone me at (615) 365-3587 (Watts Bar) if you have any questions.
Very truly yours, TENNESSEE VALLEY AUTHORITY-
-iY,$b.
M. S. Martin Watts Bar Nuclear Plant ECTG Licensing Manager cc'(See page 2.):
8706010464 870518 PDR ADOCK 05000327 go P
PDR q
-l 1
An Equal Opportunity Employer
p__- _m_-
l 2
i.
U.S. Nuclear Regulatory Commission cc (Enclosures):
Mr. G. G. Zech, Assistant Director Regional Inspections Division of TVA Projects Office of Special Projects U.S. Nuclear Regulatory Commission Region II.
101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. John A. Zwolinski, Assistant Director For Projects Division of TVA Projects Office of Special Projects U.S. Nuclear Regulatory Commission 4350 East West Highway EWW 322-Bethesda, Maryland 20018 Sequoyah Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379 5133T L.
l
I e
a
ENCLOSURE l' Page 1 of 1 SEQUOYAH EMPLOYEE ELEMENT REPORT CONCERN NUMBER ISSUE Engineering 23508 IN-85-973-003 PVC Liquidtight (Revised Final)
Flex Conduit Note: Engineering 23508 was submitted final 12/24/86. It is being revised to add Corrective Action and to revise Appendix A.
Material Control 40400 IN-85-443-002 Storage and Handling As (Revised Final)
WI-85-100-040 Related to Material Control XX-85-122-045 XX-85-122-046-XX-85-122-047
- WI-85-091-014
- Concern addressed by MC 40307.
NOTE: Material Control 40400 was submitted final 2/17/87. It is being revised to incorporate consolidated corrective action plan and NRC comments.
1
~ W g
l
ENGINEERING CATEGORY Enclosura 2 Page 1 of 2 ECTG WRITER'S GUIDE ELEMENT REPORT FORMAT 1.0 Issue 1.
Characterization of Issue (s)
Characterization 2.0 Summary 9.
Discussion, Findings and Conclusions 3.0 Evaluators Cover Sheet Information 4.0 Evaluation 8.
Evaluation Process Process
5.0 Findings
9.
Discussion, Findings, and Conclusions 6.0 Root Cause (Collective Significance)M*
- Overall Root Cause will not be considered at this report level.
7.0 Attachments /
Attachments as required List of Concerns Other items included 2.
Have issue (s) been identified in Engineering Element in another systematic Reports analysis?
3.
Document nos., tag nos.,
locations or other specific descriptive identifications stated in element.
4.
Interview files reviewed 5.
Documents reviewed related to the element 1992T 1
ENGINEERING CATEGORY Enclosura 2 Page 2 of 2 ECTG WRITER'S GUIDE ELEMENT REPORT FORMAT Other items included in Engineering Element 6.
What regulations, licensing Reports commitments, design require-(cont'd) ments, or other apply or control in this area?
7.
List requests for information, meetings, telephone calls, and other discussions related to element.
k.
me-,
a
.s 4.h,.
masma MATERIALS CONTROL ' Enclosure '2 ECTG WRITER'S GUIDE ELEMENT REPORT FORMAT 1.0 Issue I.
Introduction Characterization t
II.
Summary of Perceived Problem 2.0 Summary-IV.
Summary of Findings Conclus!ons (Portion) i 3.0 Evaluators Cover Sheet Information 4.0 Evaluation III. Evaluation Process Methodology
5.0 Findings
IV.
Summary of Findings 6.0 Root Cause V.
Root Cause (Collective Significance)**
- Overall Root Cause will i
not be considered at this report level.
a 7.0 Attachments /
VIII. Attachments List of Concerns Other items included VI.
Corrective Actions in Element (To be provided by i
Reports line organizations)
VII. Generic Applicability I
l 190ST
A ', g ~
1 l
)
I I
I 1
1
TVA EMPLOYEE CONCERNS REPORT NUMBER: 235.8 (B)
}.,;,'
SPECIAL PROGRAM REVISION NUMBER:
1 REPORT TYPE:
SEQUOYAH ELEMENT 4
TITLE:
ELECTRICAL SAFETY PAGE 1 0F 13 PVC Liquid-tight Flex Conduit REASON FOR REVISION:
Revised to add Section 10, Corrective Action, and to revise 1.
Appendix A, Subsection 7.
PREPARATION PREPARED BY N
k
$~ ~2/ cf ~7
/ DATE' SlyATURE REVIEWS gR w/,a 4Wn
-PtERT REVIE C ITTEEe D
DATE
/
SIG%TURE TAS: #
DATE SIGNATURE CONCURRENCES du/ d. ldo, Ai I?t/L S/iz/27 CEG-H:df'D7 d
S/is/tt SRP:\\cwiuJ.k S-l3-8 7 SIGNATURE DATE SIGNATURi*
OATE APPROVED BY:
'A. b ' mal 5M/fl m
ACSP MANAGER DATE MANAGER OF NUCLEAR POWER DATE i
CONCURRENCE (FINALREPORTONLY)
I CSRP Secre ry's signature d RF concurrences are in files.
\\
S'70io9e5 W
't TVA EPFLOYEE CONCERNS REPORT NUMBER: 235.8 (B)
SPECIAL PROGRAM REVISION NUM8ER:
1 PAGE 2 0F 13 l.
CHARACTERIZATION OF ISSUE (S):
Concern:
Issue:
f IN-85-973-003 a.
P1astic flex conduits installed in
" Plastic type flex conduit containment and valve rooms are installed between instruments not qualified for use because of and for all floor mounted panels the heat generated in these areas (Units 1 and 2) cannot with-and had to be changed at SQN.
stand heat generated in contain-ment and valve rooms. CI stated a friend (known) said that all such installations had to be changed at Sequoyah. CI could not provide specific panel /
conduit I.D. #'s.
Engineer (known)hasbeen' contacted,as has Knoxville engineering, but no action has been taken.
Construction department concern.
Both units.
1985."
2.
HAVE ISSUES BEEN IDENTIFIED IN ANOTHER SYSTEMATIC ANALYSIS? YES X N0 o
Date 10/21/85 4
i SCR WBNEEB8548, Conduit PVC Jacket Is Not Qualified for Environment It Is To Operate In i
o Identified by TVA WBN EQP Date 03/27/86 QIR EQP86032, Flexible Conduit Inside Containment i
o Identified by, TVA WBN E0P Date 04/29/86 j
i QIR WBNEQP86046, Flexible Conduit Inside Containment i
e f
14660-2 (04/21/87) i
~..... - -.
_.. - _JL _ Ah _, _ _... - -.
TVA EMPLOYEE CONCERNS REPORT NUMBER: 235.8 (B)
SPECIAL PROGRAM REVISION NUMBER:
1 PAGE 3 0F 13 Q
o Date 11/18/85 SCR SONEEB8526 R1, Conduit PVC Jacket Is Not Qualified for Environment It Is To Operate In DOCUMENT NOS., TAG NOS., LOCATIONS OR OTHER SPECIFIC DESCRIPTIVE 3.
IDENTIFICATIONS STATED IN ELEMENT:
However, the concern No further information is available.
identified plastic type flex conduits located in the containment and the steam valve rooms as not being qualified for the heat of the environment they are to operate in.
4.
INTERVIEW FILES REVIEWED:
File IN-85-973 was reviewed, and no additional unreviewed information of SQN was identified for the concern in this report.
DOCUMENTS REVIEWED RELATED TO THE ELEMENT:
s' 5.
See Appendix A.
WHAT REGULATIONS, LICENSING COMMITMENTS, DESIGN REQUIREMENTS OR OTHER 6.
APPLY OR CONTROL IN THIS AREA?
See Appendix A.
LIST REQUESTS FOR INFORMATION, MEETINGS, TELEPHONE CALLS, AND OTHER 7.
DISCUSSIONS RELATED TO ELEMENT.
See Appendix A.
14660-2 (04/21/87)
...n
l TVA EMPLOYEE CONCERNS REPORT NUMBER: 235.8(B)
SPECIAL PROGRAM REVISION NUMBER:
1 PAGE 4 0F 13 8.
EVALUATION PROCESS:
Reviewed available transcripts of NRC investigative a.
interviews for additional information on the concern, b.
Reviewed TVA contract No. 72C33-92800 for conformance to requirements regarding use of PVC inside containment.
Reviewed existing TVA Construction, QA/QC, Operations, and c.
Material Control reports for the TVA Employee Concerns Special Program for applicability to the concern discussed in this report.
Reviewed the tests performed by TVA and Wyle Laboratories for d.
radiation and temperature effect (n) PVC.
Reviewed existing SCRs and QIRs reports and ascertained if e.
corrective actions resolve the issue.
f.
Assessed adequacy of PVC jacket used on flexible conduits inside containment and steam valve rooms.
\\' -
9.
DISCUSSION, FINDINGS, AND CONCLUSIONS:
Chronology:
05/15/73: General Construction Specification G-3, R0 requires the use of synthetic-jacketed, liquid tight flexible conduits in all locations 08/06/75: General Construction Specification G-40 supersedes G-3; G-40 requires the use of stainless steel flex conduits inside primary containment and drywell areas 10/01/85: Concern received by TVA for WBN 10/21/85:
SCR WBNEEB8548 R0 identifies the problem and the Engineering Report for the SCR recommends testing of EF PVC-jacketed flex conduits 11/07/85:
SCR SQNEEB8526 R1 results from a generic review at SQN which identifies the use of type EF PVC flex conduits 12/11/85: Engineering Report (ER) for SCR SQNEEB8526 R1 recommends leaving existing flex conduits as is 14660-2 (04/21/87) m.
..x a
TVA EMPLOYEE CONCERNS REPORT NUMBER: 235.8 (B)
SPECIAL PROGRAM REVISION NUMBER:
1 PAGE 5 0F 13
(
12/16/85: TVA Central Laboratories tests PVC flex conduits for heat exposure 03/27/86: QlR EQP86032 states that no justification existed to replace the PVC flex conduits 04/21/86: Wyle Laboratories performs beta radiation testing on PVC flexible conduits 04/29/86: QIR WBNEQP86046 states that the PVC jacket is not essential for cable qualification against beta radiation at SQN 06/24/86: OE Calculation GENNAL3-003 R3 issued to determine post-LOCA beta dose reduction expected from the PVC jacket Discussion:
The evaluation team reviewed the different reports regarding the use of PVC-jacketed flexible conduit inside the containment and valve rooms and found several inconsistencies among them. TVA's contract No. 72C33-92800 (04/14/72, App. A, 5.b) for instrument panels located inside the containment and the north / south main steam valve rooms (MSVR) for Watts Bar and Sequoyah, specified the use of Anaconda PVC-jacketed flexible conduit type "EF."
This contract conformed to General Construction Specification G-3 (05/15/73, App. A, 5.t) which required the use of synthetic-jacketed, liquid-tight, flexible conduit in all locations.
Subsequently, General Construction Specification G-40 R0 (08/06/75, App. A, 5.d) superseded G-3.
G-40 included a requirement to use stainless steel flex conduits inside primary containment and drywell areas instead.of liquid-tight, flexible conduits.
In areas outside primary containment and drywell, synthetic-jacketed, liquid-tight, flexible conduits, Anaconda type UA or equal are required.
These UA type PVC-jacketed flex conduits have a commercial grade of Underwriters Laboratory (UL) rated PVC outer coating. The PVC outer jacket has a manufacturer's recommended operating temperature range between -4*F and 140'F.
Type EF PVC-jacketed flex conduits do not have a UL rated outer coating, but do have the same operating temperature range.
According to the panel supplier, YEP Industries Inc. (10/16/85, App. A, 5.a), the PVC-jacket becomes pliable at around 200*F and could begin to flow off the metal core at temperatures "between 200 F and 350*F."
e,g 14660-2 (04/21/87) 4 m
s& r er
TVA EMPLOYEE CONCERNS REPORT NUMBER: 235.8(B)
SPECIAL PROGRAM REVISION NUMBER:
1 PAGE 6 0F 13 The Watts Bar Engineering Report (ER) SCR WBNEEB8548 R0 (01/13/86, App. A, 5.e) issued for SCR WBNEEB8548 R0 (10/21/85, App. A, 5.c) concluded that the qualification documentation of the Anaconda type EF PVC-jacketed flexible conduits purchased under contract 72C33-92800 (WBN and SQN) was insufficient. The conduit does not meet the radiation and temperature requirements for a loss of coolant accident (LOCA) or a high energy main steam line break (MSLB) and it was considered unacceptable for use in safety-related The report recommended that a sample of type EF conduit systems.
be tested at a temperature of 360'F af ter the conduit has been irradiated to 1.2 x 108 rads. This test would determine the effects, if any, on the sealing and shielding properties of the The report stated that the PVC-jacket "is required to PVC-jacket.
shield the circuits within the conduit from beta radiation levels detrimental to the proper operations of their associated sensors,"
and also observed that the PVC-jacket would most likely become brittle during a LOCA and " flake-off" the conduit.
A generic review of SQN was initiated by SCR WBNEE88548 R0 and resulted in issuance of SCR SQNEEB8526 R1 (11/18/85, App. A, 5.1).
This SCR stated that Anaconda type EF or equivalent conduits are located in environments for which they are not qualified. To allow use of PVC-jacket that could melt, become brittle, or break off the conduit was not acceptable because credit was taken for the jacket as a beta shield. Also, if the PVC material ran onto the floor, it could plug the floor drains.
The Engineering Report SCR SQNEEB8526 R1 (12/11/85, App. A, 5.m) stated that the PVC-jacket on the flex conduit was required to protect circuits routed within the conduit and without this protection the sensors associated with these circuits could give false reading due to insulation degradation and subsequent current leakage. Ilowever, the report assumed "that the PVC material will not become brittle and fall off at 10$ rads." Therefore, the sump drains would not be clogged. Furthermore, the ER concluded that the operation of instrumentation required for safe shutdown would not be impaired due to moisture during a LOCA because instruments required to operate after a LOCA have a second moisture barrier (Conax connector or qualified seal) at the instrument to prevent moisture intrusion to the instrument even if the PVC-jacket The ER were to crack and admit moisture into the conduit.
recommended to " leave the existing flex conduit as is."
14660-2 (04/21/87)
TVA EMPLOYEE CONCERNS REPORT NUMBER: 235.8 (B)
SPECIAL PROGRAM REVISION NUMBER:
1 PAGE 7 0F 13 The Quality Information Request / Release QIR EQP86032 (03/27/86, App. A, 5.h) stated that the " flexible conduit is not a piece of class 1E equipment;" therefore, the type of flexible conduit used inside primary containment is not an Environmental Qualification (EQ) problem and the purpose of any type of raceway (including flexible contrit) is to support the cables contained therein.
It also stated that there was no justification to replace the PVC flexible conduits on existing panels for the follow reasons:
a.
" Conduits with a PVC-jacket are similar in nature to PVC-jacket were tested at 327*F and 7.5 x 10jth a cables with a PVC-jacket. For SQN, cables w
- rads, with no evidence of the PVC-jacket running off or breaking off the cable."
b.
"An in-house TVA test conducted at Central Laboratories (Report No. C186-86-1155) concluded that the PVC-jacket -
will remain intact for two hours at 360*F. The temperature for the worst case accident inside containment is 327"F for 27 minutes."
c.
"For the worst case accident, the radiation levels inside the MSVR are less than 104 rads, well below the 5.5 x 105 rads identified in SCR WBNEEB8548 R1 as the '
threshold of failure for plasticized PVC."
As mentioned above, TVA Central Laboratories tested a sample of Anaconda type EF flex conduit for heat exposure. Test report C186-86-1155 (12/16/85, App. A, 5.f) concluded that the PVC-jocket on the conduit remained intact not only for the required 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 360 F without loss of jacket material, but at 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> still showed no melting or loss of material.
Wyle Laboratories performed beta radiation testing on various specimens of PVC flexible conduit used at SQN and WBN (App. A, 5.f; 04/21/86). All test specimens received a total beta dose of 61 million rads (megarads). The test results showed that the Anaconda type EF flexible conduit jacket had slight darkening and roughening of surface texture, but remained intact.
QIR WBNEQP86046, from D. L. Kitchel to W. S. Raughley (04/29/86, App. A, 5.j) furnishes additional information concerning the and further reasoning and rationale given in QIR EQP86032 justifiesrevisingthecorrectiveactioninSURWBNEEB8548R1 (01/13/86, App. A, 5.g) which recommended replacing the PVC-jacketed flex conduits with stainless steel flex per G-40.
The QIR indicated the PVC-jacket on flexible conduit was not essential for establishing environmental qualification of the ca5Tes against beta radiation at SQN.
14660-2 (04/21/87)
- ~
TVA ElFLOYEE CONCERNS REPORT NUMBER: 235.8 (8).
.SPECIAL PROGRAM REVISION NUMBER:- 1
^
PAGE.8 0F 13 a
The environmental parameters at SQN 'and WBN are similar, and the same vendors supplied cable for'use in containment at SQN and WBN.
Consequently, there was no reason to be11 eve that the PVC-jacket on-f flexible conduit would be essential for qualification of cables at
+
SCR W8NEEB3548 R2 was issued (05/07/86, App. A, 5.k) to WBN.
l revise the corrective action as requested in the QIR for the cables i
at WBN.
OE Calculation GENNAL3-003 R3 (06/04/86) was issued to determine the reduction from free-field post-LOCA beta dose to be expected from PVC-covered conduits of different sizes inside containment.
4 This calculation states that "for equipment qualification in a i
post-LOCA environment of cable routed within such conduits the j
i attenuation provided by these conduits for beta radiation is required." This calculation is consistent with SCR SQNEEB8526 R1 for taking credit for the PVC-jacket as a beta shield. These two documents, however, disagree with QIR WBNEQP86046 which states that the PVC-jacket is not required for establishing environmental j
qualifications for cables at SQN. TVA, however, indicates (App. A, 7.b) that the PVC-jacketed conduit is not required for the environmental qualification of the cables but rather for enhancing l
their useful life by providing additional beta shielding.
i I
Review of Calculation GENNAL 3-003 R3 by the evaluation team' determined that the PVC-jacket on flexible conduits is required for environmental qualification of cables at SQN. The maximum expected total integrated dose (TID) in the lower containment (worst case) thatSQNPVCcablejacketshavebeentestedto7.5x10jndicates is in excess of 7.5 x 07 rads. Although QIR EQP86032 1
rads, no j
document could be identified' demonstrating the acceptabf11ty for using PVC-jacketed flexibly conduits when exposed to a radiation i
dose in excess of 7.5 x 10 rads.
Findings:
Various documents discuss the adequacy of PVL-jacketed f
flexible conduits inside the containment without a
i substantiating the reason or source for the conclusion.
In addition, radiation and temperature tests were performed by j
Wyle Laboratories and TVA, respectively, to demonstrate the acceptability of PVC-jacketed flexible conduit used inside i
f~
containment. None of the documents and tests performed singly makes an adecuate assessment of the acceptability of PVC-jacketed flexib'e conduits taking into consideration the environmental conditions inside containment.
b.
There is_an inconsistency between various documents defining i
the purpose of the PVC jacket as.a beta radiation shield for J
s cable qualification.
l l
14660-2 (04/21/87)
~
.m
t 235.8 (B)
TVA EMPLOYEE CONCERNS REPORT NUMBER:
SPECIAL PROGRAM REVISION NUMBER: 1 O
PAGE 9 0F 13 i
i
==
Conclusions:==
L The concern regarding PVC-jacketed flexible conduit not being qualified for use inside the containment _is valid because there is no overall assessment demonstrating the adequacy of the i
PVC-jacketed flexible conduit used inside the containment.
i i
- 10. CORRECTIVE ACTION:
CATD 235 08 SQN 01 indicated that no overall assessment was identified demonstrating the adequacy of the PVC-jacketed flexible j
conduit used inside the containment. The corrective action plan submitted by TCAB-087 (04/07/87, App. A, 5.x) indicates a i*
calculation is being performed to provide justification for the-acceptability of the existing PVC-jacketed flexible conduit used inside the containment. The calculation will be completed by 04/20/87. This corrective action provides an acceptable method and 4
schedule to resolve the problem identified by the CATO.
i 1
l CATO 235 08 SQN 02 indicated that there is an inconsistency between various documents defining the purpose of the PVC jacket as a. beta i
v radiation shield for cable qualification. This inconsistency was.
also identified during the review of the employee concern for Watts Bar. The corrective action plan submitted by TCAB-298 (03/16/87, App. A, 5.x) [for-CATD 235 08 WBN 01] indicated QIR WBN EQP86046 i
will be reviewed and modified to be consistent with the Sequoyah EQ f
program.
j i
i x
i,s, 14660-2 (04/21/87) 1
~.
_.,~.___.___....4..
TVA EMPLOYEE CONCERNS REPORT NUMBER: 235.8 (B)
SPECIAL PROGRAM
>l REVISION NUMBER:
1 PAGE 10 0F 13 APPENDIX A 5.
DOCUMENTS REVIEWED RELATED TO THE ELEMENT:
Letter from D. Dietz, YEP Industries Inc., to F. W. Chandler, a.
TVA, " Watts Bar Nuclear Plant Local Panel and Instruments Contract 72C33-92800," (B43 851016 014), (10/10/85)
TVA Contract No. 72C33-92800, " Specification 1569 for Local b.
Panels Fabrication and Instrument Installation for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2,"
(04/14/72) s SCR WBNEEB8548 R0, " Conduit PVC Jacket Is Not Qualified for Environment It Is To Operate In," (843 851023 913), (10/21/85) c.
TVA General Construction Specification G-40, R8, (10/10/75),
d.
" Installing Electrical Conduit Systems and Conduit Boxes,"
R9,(01/15/86)
TVA memo from Raulston to Cox, " Watts Bar Nuclear Plant -
e.
Ensineering Report (ER) for Significant Condition Report (SCR) WBNEEB8548 R0," (B45 851114 275), (11/14/85)
TVA's Central Laboratories Report No. C186-86-1155, " Heat f
f.
Exposure of PVC Jacketed Flexible Conduit," (843 851223 002),
(12/16/85)
SCR WBNEEB8548 R1, " Conduit PVC Jacket Is Not Qualified for Environment It Is To Operate In," (843 860121 924), (01/13/86) g.
h.
QIR EQP86032, " Flexible Conduit Inside Containment,"
(B71 860328 250), (03/27/86) 1 Letter from H. B. Bruce, Wyle Lab., to W. S. Raughley, TVA, 1.
" Experimental Determination of Beta Reduction Factors for TVA Conduit Specimens Contract TV-56071A," (843 860425 005),
1 (04/21/86) j.
QIR WBNEQP86046, " Flexible Conduit Inside Containment,"
(B71 860429 250), (04/29/86)
TVA memo from Raughley to Raulston, " Watts Bar Nuclear k.
Plant - Significant Condition Report SCR WBNEEB8548 R2,"
(B43 860616 962), (06/10/86)
(
l 1466D-2 (04/21/87)
%n.
a s
'9.
TVA EWLOYEE CONCERNS REPORT NUMBER: 235.8 (B)
SPECIAL PROGRAM REVISION NUMBER:
1 PAGE 11 0F 13 APPENDIX A (Cont'd)_
SCR SQNEEB8526, " Conduit PVC Jacket Is Not Qualified for 1.
Environment It Is To Operate In," (B25 851113 810), R0 (11/07/85), (B25 851120 820), R1 (11/18/85)-
TVA memo from Vineyard to Rankin, "Sequoyah Nuclear Plant m.
Units 1 and 2 - Engineering Report for CAQ(Report No. SCR SQNEEB8526 Revision 1," (B25 851211 018), 12/11/85)
Anamet Inc., Sealtite "EF" Conduit Catalog (formerly Anaconda n.
Metal Hose Division of Anaconda American Brass Co.)
QIR WBNEEC86007, " Flexible Conduit Inside Containment,"
o.
(B26 860123 009), (01/23/86)-
Letter'from E. Chitwood, TVA, to F. Sittason, Wyle Lab.,
p.
"Sequoyah and Watts Bar Nuclear Plants Test Procedures for Beta Radiatien Testing of Various Flexible Conduits Installed in TVA - TVA Contract TV-56071 A," (843 860411914), (04/10/86)
TVA memo from Raughley to Those Listed, " Watts Bar Nuclear i
q.
Plant s Significant Condition Report SCR WBNEEB8548 R2,'A (B43 860322 907), (05/07/86)
SNP FSAR, Section 3.11.1, " Environment Data Reactor / Auxiliary r.
Building" Electric Power Research Institute, EPRI NP-2129, " Radiation s.
Effects on Organic Materials in Nuclear Plants,"
(870351030101),(11/81)
TVA General Construction Specification G-3'R0, " Installing t.
Electrical Conduit Systems and Fabricated Conduit Boxes,"
(05/15/73)
..u.'
Letter.from B. J. Youngblood, NRC, to S. A. White, TVA,
' (B45 660114 532), (06/23/86) with the attached transcript of j>
4 the investigative interview conducted by the NRC on 02/21/86 at the First Tennessee Bank Building in Knoxville, TN QE Calculations GENNAL3-003 R3, " Beta Dose Reduction by v.
PVC-Coverd Conduit Inside Primary Containment,"
(B45 860624 236), (06/24/86)
Environmental Qualification (EQ) binder SQNEQ-CABL-009, TAB B w.
i and C, Rev. 1,(08/01/86)
);
14660-2 (N /21/07)
+.,
,j.
4
+$2^
f
TVA EMPLOYEE CONCERNS REPORT NUMBER:
235.8 (B) o SPECIAL PROGRAM REVISION NUMBER:
1 PAGE 12 OF 13 1
APPENDIX A (Cont'd).
Corrective Action Plan (CAP) for CATDs 235 08 SQN 01 and SQN 02 x.
transmitted via TCAB-087 (04/07/87) and TCAB-298 (03/16/87)
WHAT REGULATIONS. LICENSING COMMITMENTS. DESIGN REQUIREMENTS OR 6.
APPLY OR CONTROL IN THIS AREA 7 TVA Contract No. 72C33-92800 a.
General Construction Specifications, G-40, R9, Section 2.3 b.
LIST REQUESTS FOR INFORMATION. MEETINGS. TELEPHONE CALLS. AND OTHER 7.
DISCUSSIONS RELATED TO ELEMENT.
Telecon from Wheeler, Bechtel, to Pickard, Anaconda, IOM 067, a.
If, (04/10/86)
\\t Telecon from Wheeler, Bechtel, to Nesbitt/ Reagan, TVA,'
b.
IOM 530, (01/14/87)
Telecon from Rieder, Bechtel to Gor, Bechtel, IOM 914, c.
(04/14/87) 1':
14660-2.(04/21/87)
- ~,., om s.t 2,.,
m n.
g g..
TVA EMPLOYEE CONCERNS REPORT NUMBER: 235.8 (B)
'-~
SPECIAL PROGRAM REVISION NUMBER:
1 k
'. }
PAGE 13 0F 13 CATD LIST The following CATDs identify and provide corrective actions for the findings included in this report:
235 08 SQN 01 (Issue "a"; 04/07/87) 235 08 SQN 02 (Finding "b"; 03/16/87) 4 0
4 b
i 9
l
./
l
~
1466D-2 (04/21/87)
=..-
~',
REFERENCE
- ECPS120J-ECPS121C TENNESSEE VALLEY AUTHORITY PAGE 83...
FREQUENCY
- REQUEST OFFICE OF NUCLEAR POWER RUN TIME - 13:58:39 I
ONP - ISSS - RHM EMPLOYEE CONCERN PROGRAM SYSTEM (ECPS)
RUN DATE - 03/19/87 EMPLOYEE CONCERN INFORMATION BY-CATEGORY / SUBCATEGORY CATEGORY: EN DES PROCESS & OUTPUT SUBCATEGORY: 23508 PVC LIQUIDTIGHT FLEX CONDUIT
- C S
H 1 REPORT APPL SUB R PLT 2 SAF RELATED HISTORICAL CONCERN CONCERN NUMBER CAT CAT D LOC BF BL SQ HB REPORT ORIGIN CONCERN DESCRIPTION
('
=_
----------=
_=_
IN 973-00301 EN 23508 N HBN 1N N Y Y QTC PLASTIC TYPE FLEX CONDUIT INSTALLED BETHEEN INSTRU-T50156 2 NA NA SR SR MENTS AND FOR ALL FLOOR MOUNTED PANELS (UNITS 1 8
, ('
- 2) CANNOT WITHSTAND HEAT GENERATED IN CONTAINMENT AND VOLVE ROOMS. CI STATED A FRIEND (KNOWN) SAID f>
THAT ALL SUCH INSTALLATIONS HAD TO BE CHANGED AT S EQUOYAH. CI COULD NOT PROVIDE SPECIFIC PANEL /COND
( ;"
UIT I.D.
S'S.
ENGINEER (KNOHN) HAS BEEN CONTACTED
,.AS HAS KNOXVILLE ENGINEERING, BUT NO ACTION HAS Ai BEEN TAKEN. CONSTRUCTION DEPT. CONCERN. 'BOTH UNI TS. 1985. CI HAS NO MORE INFORMATION. NO FOLLOW (7
sp 1 CONCERNS FOR CATEGORY EN SUBCATEGORY 23508
\\
. C'
..)
u 4
.i
}
($
pg2
-(.
95 I) 1 (v 1:
.j r i C;
- i NA.'
....,..w--.-,.,.
-,,- ~
- x
..Y, e
s q
g,
s
- *