ML20214J243
| ML20214J243 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/13/1986 |
| From: | Gass K, Knightly J, Stewart D TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20214H850 | List:
|
| References | |
| SWEC-SQN-38, SWEC-SQN-38-R, SWEC-SQN-38-R00, NUDOCS 8612010223 | |
| Download: ML20214J243 (7) | |
Text
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f TVA EMPLOYEE CONCERNS REPORT NUMBER: SWEC-SQN-38 SPECIAL PROGRAM REPORT TYPE: Sequoyah Nuclear Plant Element REVISION NUMBER: 0 i
TITLE: Maintenance Management REASON FOR REVISION: N/A SWEC
SUMMARY
STATEMENT: The items in this report were identified by the Nuclear Regulatory Commission (NRC) and were included in the Stone & Webster Engineering Corporation (SWEC) systematic analysis. All items evaluated within this report were verified to be adequately addressed and SWEC concerns A02 850809 036 -001 and -002 were closed by NRC. Concern A02 850809 036 -003 will be ready for closure following completion of SQN workplan activities now in progress.
PREPARATION PREPARED BY:
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CONCURRENCE (FINAL REPORT ONLY) ,
- SRP Secretary's signature denotes SRP concurrences are in files.
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TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT EMPLOYEE CONCERNS TASK GROUP OTHER SITES CEG i
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Element: Maintenance Management
, SWEC Concerns: A02850809036-001
-002
-003
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' Source Document: NRC Inspection Report 327, 328/85-24 Report Number: SWEC-SQN-38 i
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l Evaluator: /0 0/hh J. J. Knightly Date f
Reviewed by: M /o/or gl, j A. G. ,Debbadje atd Approved by: My /d[dt[f[,
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Report: SWEC-SQN-38
'"l' NRC Reports: 50-327/85-24 and 50-328/85-24
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' I. INTRODUCTICNT' .
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- During an unannounced inspect?on i3f June 17-21, 1985, iNvolvingthe
' Sequoyah Nucleae. plant (SQN) maintenance program, the Nuclear Regulatory I
Commission (NRC) . identified one area of conc 5rn and two, violations which
,, were includedlin the Stone & Webster Engineering Corporation (SWEC) systematic andlysis:
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A. A02650809036-001 - Lack of a firm management commitment to the
, maintenance management system.
N7 B. A02850809036-OO2 - Performance of post maintenance testing.
- s C. A02850809036-003 - Monitoring the ice cdndenser bed temperatures.
Information on the bac,kground, corrective 'a,c'tions'taken, verification
' methodology and analysis, completion status,' and any pertinent references for,thistarea of concern and these two violations is included in this repoqt. 'l~ .
II. VERIFICATION OF THE SOEC ISSUES
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<. A . A01650809036-001, Maintenance - Lack of Management Commitment
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- 1. Backg round TheNRCcoverletterforthisinspechion"(referenceA) called
' attention to the lack of a firm time commitment by SQN management to correct several concerns dealing with the maintenance management. system. These concerns hai been identified as Inspector Follow-up Item (IFI) 327,328/85-24-01.
SQN stated during the inspection that the listed concerns would be ? addressed and corrected but that a firm commitment date for
' completion could not be given.
- 2. Corrective Actions Taken s"
TVA has placed special emphasis on maintenance in the Nuclear Performance Plan, Volumes I and II. The Nuclear Manager's 3 Review Group conducted a maintenance review which included SQN from May 19, 1986 through June 13, 1986 (reference L). In addition, NRC's 1986 review of maintenance activities at SQN found 'that " progress was noted on most items, and improvement in
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the overall maintenance program was apparent" (reference H).
,s s The IFI was closed by the NRC in Inspection Report 327,328/86-18 (referen'ce F). '
- 3. Verification Methodology '
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ThE SWEC con}. erns identified for Employee Concerns Task Group (ECTG) verification was stated as follows:
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RIMS Number Issue RIMS Item A02850809036 NRC is concerned by the lack of RIMS-001 a firm commitment by SQN manage-
' ment to correct several concerns '
0 dealing with TVA/SQN maintenance management system
~' ECTG reviewed the SQN Compliance Licensing files for internal and external correspondence related to this issue and the TVA Nuclear Performance Improvement Plan. This review of the pertinent documentation formed the basis for this verification activity.
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- ] 4. Verification Analysis i
- The ECTG review of the pertinent documentation indicated that
' improvements in the maintenance program have occurred and that the program is progressing as noted under " Corrective Actions j Taken" (II.A.2).
1 1 5. Completion Status g
5 j Based on SQN actions and evidence of SQN management commitment, 1 corrective action on the SWEC issue is assessed to be 9
progressing satisfactorily. This issue is closed.
9 j B. A02850809036-002, Post Maintenance Testing
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- 1. Background j The NRC inspector determined that an appropriate post maintenance flow rate test on the Emergency Gas Treatment System (EGTS) was not performed after an EGTS damper was repaired on June 18, 1985. NRC felt there was a lack of adequate criteria to determine the need for a post maintenance test as required by
, Technical Specification 6.8.1.a. This was identified as ij violation 328/85-24-02.
N l} 2. Corrective Actions Taken
' SQN reported (reference B) that a satisfactory flow rate test was performed in accordance with Surveillance Instruction-142 j.
' " Emergency Gas Treatment System Filter Train Test" on July 19, 1985. Standard Practice SQM 2, " Maintenance Management System,"
revision 18, (February 27, 1986), was revised to specify when a post maintenance test is required for maintenance activities and descriptions of what should be required in the test.
- 3. Verification Methodology The SWEC concern identified for ECTG verification was stated as follows:
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k RIMS Number Item RIMS Item A02850809036 Due to a lack of adequate criteria RIMS-002 for post MX test, TVA failed to conduct appropriate MX flow rate test on EGTs after completing an EGTs damper repair.
ECTG reviewed the applicable procedura and the SQN Compliance Licensing files for internal and external correspondence related to this issue. This review of the pertinent documentation formed the basis for this verification activity.
- 4. Verification Analysis The ECTG review of the pertinent documentation indicated that the NRC item was adequately resolved. Post maintenance test criteria were placed into the Standard Practice SQM 2. The NRC verified the satisfactory revision to SQM-2, and closed the violation in inspection report 327,328/C6-06 (reference G).
- 5. Completion Status Based on the SQN corrective actions, compliance with requirements, and NRC closure of the item, no further action on this item is required. This item is closed.
C. A02850809036-003, Ice Condenser
- 1. Background The NRC inspection of the ice condenser, unit 2, determined that on June 10 and 16, 1985, there was ice buildup on the intermediate door in violation of Technical Specification (TS) surveillance instruction 4.6.5.3.2. The inspector also determined that a lack of adequate post maintenance criteria resulted in recording the ice bed temperature once for each eight-hour shift instead of once every four hours as required by TS 3.6.5.3. NRC identified this as violation 85-24-03.
- 2. Corrective Actions Taken SQN stated (reference B) that Technical Specification 3.6.5.3 allows the flexibility, in lieu of recording the ice bed temperature, to ". . . otherwise, restore the doors to their closed positions or operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />." SQN stated that the ice was removed on June 10 and 19, 1985, and the intermediate deck doors were returned to operable status within the 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prescribed by the TS. In response to this, NRC stated (reference K) their view that more acceptable ice conditions should be ensured by SQN.
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- 3. Verification Methodology The SWEC concerns identified for ECTG verification was stated as follows:
RIMS Number Item RIMS Item A02850809036 Due to a lack of adequate post RIMS-OO3 maintenance criteria, TVA failed to monitor ice condenser bed temperatures at the required periodicity.
ECTG reviewed the SQN Compliance Licensing files for internal and external correspondence related to this issue. This review of the pertinent documentation, in addition to discussions with Power Plant Maintenance personnel, formed the basis for this verification activity.
. 4-. Verification Analysis The ECTG review of the pertinent documentation indicated a view by SQN (reference B) that a cause of the ice buildup was increased containment humidity from steam leakage through the steam generator manway, a leakage which was subsequently corrected. In addition, SQN prepared an SQN surveillance instruction, SI-108, " Ice Condenser Intermediate Deck Doors -
Visual Inspection, Lift Test and Ice Removal" (Revision 0, November 27, 1985). This, with corrective actions outlined j above, wh a regarded as adequate corrective action by SQN.
However, during a follow-up inspection several months later (reference F), the NRC inspector found icing problems which
! prevented violation 85-24-03 from being closed. The violation remained open at the time of ECTG verification. The SQN Power Plant Maintenance Engineer stated to ECTG September 22, 1986, that additional work was needed to remove the causes of the ice buildup. It was verified that workplans 11872 (unit 1) and 11873 (unit 2) had been issued to (1) install insulation behind
' the vent curtain which surrounds the condenser, and (2) insulate the radial beams that support the upper deck doors in order to eliminate condensation falling from above onto the doors. It s was the view of the engineer that this work would effectively
[ deal with the icing problems.
! 5. Completion Status Following completion of workplan activities, SQN expects that
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the ice condenser ice buildup problems will be resolved, and that the NRC violation in this area will be ready for closure.
l Following NRC closure, the SWEC issue can be closed.
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III. REFERENCES A. NRC Inspection Report Nos. 50-327/85-24 and 50-328/85-24, dated August 7, 1985, from R. D. Walker to H. G. Parris B. "Sequoyah Nuclear Plant Units 1 and 2 - NRC-OIE Region II Inspection Report 50-327/85-24 and 50-328/85 Response to Violations,"
dated September 6, 1985, from J. A. Domer to J. N. Grace C. l-
"Sequoyah Nuclear Plant Units 1 and 2 - NRC-OIE Region II Inspection
- Report 50-327/85-24 and 50-328/85 Supplemental Response to Violation," dated October 4, 1985, from J. A. Domer to J. N. Grace D. "Sequoyah Nuclear Plant Units 1 and 2 - NRC-OIE Region II Inspection -
Report 50-327/85-24 and 50-328/85 Revised Response to }
Violation," dated October 24, 1985, from J. A. Domer to J. N. Grace E. NRC Inspection Report Numbers 50-327/85-24 and 50-328/85-24, dated September 25, 1985, from R. D. Walker to H. G. Parris F. NRC Inspection Report 50-327/86-18 and 50-328/86-18, dated !
April 9, 1986 I G. NRC Inspection Report 50-327/86-06 and 50-328/86-06, dated March 5, 1986 t
H. NRC Inspection Report 50-327/86-18 and 50-328/86-18, dated April 9, 1986 :
f I. Surveillance Instruction SI-142, " Emergency Gas Treatment System Filter Train Test" J. SQN Standard Practice SQM 2, " Maintenance Management System" K. NRC Memorandum, " Report Numbers 50-327/85-24 and 50-328/85-23,"
dated April 21, 1986, from J. A. Olshinski to S. A. White l
l L. Memorandum from R. L. Gridley to H. R. Denton, dated August 2, 1986, transmitting draft report R-86-02-NPS, " Review of Maintenance at 4
Browns Ferry, Sequoyah, and Watts Bar Nuclear Plants" J
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