ML20214V800
| ML20214V800 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/15/1986 |
| From: | Howard J, Russell J TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20214T770 | List: |
| References | |
| CO10307-SQN, CO10307-SQN-R05, CO10307-SQN-R5, NUDOCS 8612090844 | |
| Download: ML20214V800 (14) | |
Text
i TVA EMPLOYEE CONCERNS REPORT NUMBER: C010307-SQN SPECIAL PROGRAM REPORT TYPE: Sequoyah Nuclear Plant Element REVISION NUMBER: 5 (Final Report)
TITLE: Uncoated Welds as Related to Construction PAGE 1 0F 4 REASON FOR REVISION:
Incorporate TAS and SRP comments and Finalize Report - - - - - - Revision 1
-Incorporate TAS and SRP cosuments and to add Corrective-Action - Revision 2 Revised Introductory Statement - - - - - - - - - - - - - - - - - Revision 3 Incorporate TAS and SRP coussents - - - - - - - - - - - - - - - - Revision 4 Incorporate Line Management's response - - - - - - - - - - - - - Revision 5 PREPARATION PREPARED BY
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~6 I SIGNATURE DATE Of ll b SIGNATURE DATE CONCURRENCES CEG-K D l ll*)4' ~/h S w . t-d! //-/5-8C SIGNATURE DATE SIGNATURE
- DATE APPROVED BY:
lblY- h N/A ECSP MANA48R DATE MANAGER OF NUCLEAR POWER DATE I CONCURRENCE (FINAL REPORT ONLY)
- SRP Secretary's Signature Denotes SRP Concurrences Are In Files.
1302T 8612090844 861120
~
TVA ENP14YEE CONCERNS REPORT NUNBER: C010307-SQN SPECIAL PROGRAM REVISION NUNBER: 5 PAGE 2 0F 4 I. INTRODUCTION This report addresses two concerns, IN-85-243-002 and IN-85-833-001, which were determined to be generic to Sequoyah Nuclear Plant (SQN) by the Watts Bar Nucleer Plant (WBN) Employee Concerns Task Group (ECTG) evaluation. These two concerns questioned the decision to leave welds and other structural items above the decontamination dado uncoated.
Concerns EX-85-059-001, IN-85-192-002, IN-85-273-001, and IN-85-451-001 were applicable to this element at WBN and included in the ECTG data
, base as being generic to SQN. These four concerns were evaluated at SQN in the Welding Project Generic Employee Evaluation Report WP-08-SQN
- to avoid duplication in the element reports between categories.
II.
SUMMARY
OF PERCEIVED PROBLEMS The concerned employee (s) perceived that:
e A. Hangers and structural steel members, including applicable welds over six feet off the floor have not been painted in the Reactor and Auxiliary Buildings.
'i B. Topcoat of paint was deleted as a requirement above six feet from i floor, therefore, adversely affecting washdown for radiological i . decontamination, t
III. EVALUATION METHODOLOGY i
A. Reviewed GEC WP-08-SQN, GCTF Unpainted Hangers and WBECTG reports on subject concerns for pertinent information.
B. Reviewed baseline evaluation of coatings initiated in response to j SQN-CAR-86-01-001.
A j C. Conducted field review to observe condition of coatings on welds.
J j D. Reviewed applicable specifications and drawings as indicated in 1 findings.
1 l E. Interviewed knowledgeable painter foremen.
l
TVA EMPLOYEE CONCERNS REPORT NUMBER: C010307-SQN l SPECIAL PROGRAN REVISION NUMBER: 5 PAGE 3 OF 4 IV. SUNNARY OF FINDINGS A. Concern IN-85-243-002 addresses hangers, structural steel members and associated welds. Field evaluation, as a part of this, confirms the SQN-CAR-86-01-001 baseline evaluation findings that there were some rusty welds on steel members. The rusting welds were the result of current modification and repairs-not design requirements at SQN.
B. Concern IN-85-833-001 addressed the lack of topcoat above the 6-foot dado for decontamination in most areas where "smee.rable" contamination may be present. The requirements for application of decontamination coat up to a 6-foot dado in coating service levels I and II areas were established from the experience at the Browns Ferry Nuclear Plant and to meet the As Low As Reasonably Achievable (ALARA) commitments. Carbon steel, including welds above the 6-foot dado, should be primed for corrosion protection. Corrosion protection for carbon steel should be provided in areas of high humidity and temperature such as inside the containment crane wall where temperatures will range up to 98'F and the humidity will be in the 98 percent range and in the valve rooms where temperatures are high, and rain can find its way into the area. Welds and/or carbon steel above the 6-foot dado are not required to meet decontamination requirements. Rusting of carbon steel creates a problem of (1) decontamination, (2) adhesion of coatings, and (3) is an indication of structural deterioration (this depends on the extent and rate of corrosion).
CONCLUSIONS A. Although this concern is valid, it has no safety significance.
Rusty welds and structural steel members should be scheduled for coatings repair as they are identified.
Based on the evaluation findings of this report and the l SQN-CAR-86-01-001 baseline, corrective action on rusty welds l will be required where Maintenance Requests (MR) for coating IRS repairs are being written in accordance with Modification and l Repair Procedures. The NRs will be cross-checked with the l baseline evaluation to assure all coatings are repaired.
B. This concern could not be validated. In accordance with the drawings and specifications, improper deletion of topcoating or limiting of coating in general has not occurred at SQN.
V. ROOT CAUSE None
TVA EMPLOYEE CONCERNS REPORT NUMBER: C010307-SQN SPECIAL PROGRAN REVISION NUMBER: 5 PAGE 4 0F 4 VI. CORRECTIVE ACTION Line Management's Response: l l
1 Rusting conditions were found during implementation of the following 1 Preventive Maintenance packages: l 1
PN-1474-364 PM-1521-364 i PN-1434-364 PN-1436-364 IR5 PM-1435-364 PN-1437-364 i PN-1439-364 PM-1473-364 i PN-1438-364 PM-1518-364 l PN-1520-364 PN-1519-364 l l
These Preventivo Maintenance packages are being evaluated by DNE. All I rusting conditions have been given a repair priority of 2. Priority 2 l items are not required for restart. Maintenance Requests and Work l Releases will be generated on these items. (CATD 10307-SQN-01) l VII. GENERIC APPLICABILITY None VIII. ATTACKNENTS Attachment A - Listing of concerns indicating safety relationship and generic applicability.
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. CD REPORT 6' ABOVE FLOOR IN THE REACTOR BLDG.
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HHYY NS TOP CDAT OF PAh'HT HAS DELETED AS A R i . x. IN -B5-833-001 CO 10300 N HBH EQUIREMENT ABOVE 6'( ABOVE FLOOR LEVE REPORT .
T50084 L) IU UNIT 1 REACTOR BUILDING. ITEH
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. CONCERHED THAT THIS COULD ADVERSELY
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ENGINEERIP!G CATF. GORY Enclosuro 3 s, ,
. \ Page } of 2 ELEMENT REPORT FORMAT 'l ECTG WRITER'S GUIDE 1.0 Issue 1. Characterization of Issuu(s) e.
Characterization ,
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- 9. Discussion, Findings and 4 j 2.0 Summary Conclusions 1
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(L 3.0 Evaluatc.s '-
[- Cover Sheet Information -
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4.0 Evaluation 8. Evaluation ?rocess
Process 3
.3 -_
7 3 5.0 Findings - 9. Discussion, Firhirigs, and.
Canslusionpc .
6.0 Root Cause s ,_ .
(Collective Significance)H W ' OveraQ Root Cause will; not b9 considered at this report, level. ., 3 y
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7.0 Attachments / Attachments as required 'N
. List of Concerns ,
Other items included 2. Have issue (s) b$en identif ed in Engineering Element in another sy'st'asicic
- Reports analysis? g ,
.' G
- 3. Document no s . , t% n so . ,
4, locations or other 4Mcific ,
descriptive 1dentifications~
- tN stat 6 in element 3 s .,
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- 4. Intervis,' files reviewed-
- 5. ' Documents reviewed related to ,
the element 1992T 1
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ENGINEERING CLTEGORY Enc 1csuro 3 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.
l l
OPERATIONS CATEGORY Enclosure 3 OPERATIONS (OP) ELEMENT REPORTS NOTES /CO!O!ENTS ECTG WRITER'S GUIDE Issue I. Title The brief introduction 1.0 Very brief introduction touches on the source of Characterization the concerns.
I. Title 1. The Conclusions are Summary 2.0 Very brief introduction towards the end of the findings.
III. Finding (Conclusions) 2. The Conclusions services as a sunnary of the findings.
f 1. The printed name of the Evaluators Cover Sheet 3.0 original evaluator (s) appears on the cover sheet,
- 2. The peer reviewer and i CEG-H approval signa-tures are also on the cover sheet.
4.0 Evaluation II. Specific Evaluation Nethodology Process III. Findings
5.0 Findings
1 1880T
EI lectro 3 OPERATIONS (OP) EIJtENT REPORTS NOTES /M- =~T5 ECTG FRITER'S GUIDE Root Cause IV. Root Cause 1. At the element level 6.0 the Root Cause is often (Collective Significance) not identifible.
- 2. Collective significance is not addressed at the element report level.
7.0 Attachments / II. Specific Eva'luation 1. A list of the concerns List of Concerns Methodology with text are included within this section.
- 2. Other reports are sometimes attached.
CONSTRUCTION CATEGORY Eiclesuro .3 BCTG WRITER'S GUIDE ELRNENT REPORT FORMAT 1.0 Issue I. Introduction Characterization II. Summary of Perceived Problem 2.0 Summary IV. Summary of Findings conclusions (Portion) 3.0 Evaluators Cover Sheet Information 4.0 Evaluation III. Evaluation Process Nethodology 5.0 Findings IV. Summary of Findings 6.0 Root Cause V. Root Cause (Collective Significance)** ** Overall Root Cause will not be considered at this report level.
l 7.0 Attachments / VIII. Attachments
! List of Concerns
! Other items included VI. Corrective Actions
' in Construction Element (To be provided by Reports line orgainzations)
VII. Generic Applicability l
i 190ST l
Encicsura 4 Page 1 of 4 EMPLOYEE SEQUOYAH CONCERN ELEMENT REPORT NUMBER ISSUE Engineering 21301 WI-85-100-010 Inadequate Management, (Initial) XX-85-122-030 Control and Status XX-85-122-031 Listing of AC and DC XX-85-122-032 Electrical Loads.
Including Diesel Generator Martins Engineering 22110 SQN-86-001-02 Use of Snubber (Initial)
Engineering 22203 EX-85-061-004 Drawing Do Not Always (Initial) OE-QMS-8 Show Weld Size Engineering 23206 IN-85-400-002 Rubber Gasket (Initial) Deterioration Engineering 22500 WI-85-100-006 Battery Support Design (Final) XX-85-122-017 XX-85-122-018 XX-85-122-019 Note: An initial report was not necessary.
This will be the only submittal for EN 22500.
Operations 30403 IN-85-945-001 Cable Problems in (Final) Manholes Note: Initial report transmitted 11/4/86.
Operations 30711 XX-85-116-001 Management (Final) XX-85-116-003 Nonresponsiveness XX-85-116-006 XX-85-116-014 OW-85-001-002 TAK-86-007 Note: An initial report was not necessary.
This will be the only submittal for EN 30711.
F:
Enclosura 4 Page 2 of 4 EMPLOYEE SEQUOYAH CONCERN ELENENT REPORT NUMBER ISSUE SWEC-11 A02-841123-007-001 SQN Refueling (Final) Procedure Violation Note: An initial report was not necessary.
This will be the submittal for SWEC-11.
SWEC-19 A02-850103-007-001 Valve Checklist; Fuel (Final) A02-850103-007-002 Handling Instruction Note: An initial report was not necessary.
This will be the only submittal for SWEC-19.
SWEC-24 A02-850311-001-001 Thimble Tube Ejection (Final) A02-850311-001-002 Event A02-850311-001-003 A02-850501-002-001 Note: An initial report was not necessary.
This will be the only submittal for SWEC-24.
SWEC-25 A02-850328-004-001 Safeguards Violation /
(Final) Inspection Follow-up Item Note: An initial report was not necessary. This will be the only submittal for SWEC-25.
SWEC-35 A02-850722-020-001 Inadequate Design (Final) A02-850722-020-002 Records; Inadequate Review Environmental Note: An initial report Question Determinations was not necessary. l This will be the only submittal for SWEC-35.
j SWEC-41 A02-850910-002-001 Electrical Problem, j
(Final) A02-850910-002-002 Radiological Protection, A02-850910-002-003 and Security Violation A02-850910-002-004 Note: An initial report was not necessary. This will be the only submittal for SWEC-41.
7 Enclcsurs 4 I Page 3 of 4 EMPLOYEE SEQUOYAH CONCERN ELEMENT REPORT NUMBER ISSUE SWEC-42 A02-850913-005-001 SQN Emergency Plan (Final) Modification Note: An initial report was not necessary.
This will be the only submittal for SWEC-42.
SWEC-43 A02-850930-016-001 High Failure Rate for (Final) Auxiliary Feedwater System.
Note: An initial report was not necessary.
This will be the only submittal for SWEC-43.
SWEC-44 A02-851007-012-001 Operational Safety (Final) A02-851007-012-002 Verification.
A02-851007-012-003 A02-851007-012-004 A02-851007-012-005 Note: An initial report was not necessary.
This will be the only submittal for for SWEC-44.
A02-851101-010-001 Surveillance, Frisking SWEC-45 and SWEC-51 (Final) A02-851101-010-002 and Outage Work.
A02-851101-010-003 A02-851216-011-001 Note: Initial reports were not necessary.
This will be the only for SWEC-45 and SWEC-51.
SWEC-46 A02-851101-011-001 Cable Tray Support (Final) A02-851101-011-002 Systems; CVCS Sampling A02-851101-011-003 Line Cracks Note: An initial report was not necessary.
This will be the only submittal for SWEC-46.
SWEC-47 A02-850412-010-001 Environmental (Final) A02-851118-005-001 Qualification Note: An initial report was not necessary.
This will be the only submittal for SWEC-47.
Enclosure 4 I I
Page 4 of 4 EMPLOYEE SEQUOYAH CONCERN ELEMENT REPORT NUMBER ISSUE SWEC-53 A02-860115-005-001 Containment Leak Rate A02-860115-005-002 Test; Prevention of (Final)
Inadvertent Procedure Changes Note: An initial report was not necessary.
This will be the only submittal for SWEC-53.
SWEC-56 LOO-841231-007-001 Leak Rate Testing Group (Final) Organization Note: Concern L00-841231-007-001 was added after 9/26/86. An initial report was not necessary. This will be the only submittal for SWEC-56.
SWEC-57 L44-850801-112-001 Draft Generic Emergency (Final) Prepareness Plan Note: An initial report was not necessary.
This will be the only submittal for SWEC-57.
Concern L44-850801-112-001 was added after 9/26/86.
SWEC-59 L99-851212-026-001 ANI Inspection Report--
L99-851212-026-002 Material Handling (Final)
L99-851212-026-003 L99-851212-026-004 Note: An initial report was not necessary.
This will be the only submittal for SWEC-57. Concerns L99-851212-026-001,002, 003 and 004 were added after 9/26/86.
Construction 10307 IN-85-243-002 Uncoated Welds As (Final) IN-85-833-001 Related to Construction EX-85-059-001*
IN-85-192-002*
IN-85-273-001*
IN-85-451-001*
IN-86-273-001**
XX-85-087-001***
- Concerns addressed in WP-08-SQN.
- Concern deleted after 9/26/86
- Concern addressed in OP 30107.
Note: Initial report transmitted 10/21/86.