Rev 0 to SWEC-SGN-45 & SWEC-SGN-51, TVA Employee Concerns Task Group,Other Sites:Surveillance,Frisking & Outage Work. Source Documents Insp Repts 50-327/85-32,50-328/85-32, 50-327/85-38 & 50-328/85-38| ML20214V649 |
| Person / Time |
|---|
| Site: |
Sequoyah  |
|---|
| Issue date: |
10/03/1986 |
|---|
| From: |
Debbage A, Knightly J, Sauer R
TENNESSEE VALLEY AUTHORITY |
|---|
| To: |
|
|---|
| Shared Package |
|---|
| ML20214T770 |
List: |
|---|
| References |
|---|
| SWEC-SQN-45, SWEC-SQN-45-R, SWEC-SQN-45-R00, SWEC-SQN-51, NUDOCS 8612090773 |
| Download: ML20214V649 (7) |
|
|
|---|
Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20210L4361999-08-0202 August 1999
Cycle 9 12-Month SG Insp Rept
ML20210L4451999-07-31031 July 1999
Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept
ML20211F9031999-06-30030 June 1999
Cycle 9 Refueling Outage
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML20205B6631999-02-28028 February 1999
Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys
ML20198S7301998-12-31031 December 1998
Cycle 10 Voltage-Based Repair Criteria 90-Day Rept
ML20199J2571998-01-31031 January 1998
Cycle 9 Voltage-Based Repair Criteria 90-Day Rept
ML20199J2441998-01-29029 January 1998
Snp Unit 2 Cycle Refueling Outage Oct 1997
L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997
SG Secondary Side Loose Object Safety Evaluation
ML20203B9591997-09-18018 September 1997
Pressure Locking Summary & Evaluations Using Commonwealth Edison Methodology for Sqn
ML20210J1761997-07-31031 July 1997
Unit 1,Cycle 9 Alternate Plugging Criteria 90 Day Rept
ML20138D1991997-04-0404 April 1997
Special Project97-928S, Sequoyah Nuclear Plant Assessments
ML20138C5371997-03-24024 March 1997
Rev 0 to Pressurizer Level Event
ML20217G2401997-03-0303 March 1997
Non-proprietary Rev 0 to SE of Reduced Thermal Design Flow
ML20117J3611996-08-0101 August 1996
SE of Safety Valve Setpoint Tolerance Relaxation
ML20117K9461996-03-0505 March 1996
Reliability Study
ML20117K9511996-02-29029 February 1996
Reliability Common Cause Assessment, for Feb 1996
ML20095J1891995-10-0505 October 1995
Design & Analysis of Weld Overlay Repair for Sequoyah Unit 1 CRDM Lower Canopy Seal Welds
ML20081D3831995-03-12012 March 1995
Simulator Four Yr Test Rept for 950312
ML20083N9521994-11-16016 November 1994
10CFR50.59 Rept to Nrc
ML20024H8491993-07-19019 July 1993
Evaluation of Ultrasonic Test Results from 1993 ISI on Underclad Flaw Indications in Sequoyah,Unit 1 Rv Nozzles.
ML20118D1941992-09-21021 September 1992
Technical Rept on Hydrogen Control Measures & Effects of Hydrogen Burns on Safety Equipment
ML20114A6641992-08-15015 August 1992
920619 Self-Assessment. Several Hardware & Software Enhancements to Emergency Response Ctrs Completed During Reporting Period
ML20141M1341992-03-27027 March 1992
Spent Fuel Pool Mod for Increased Storage Capacity
ML20029C2011991-03-12012 March 1991
Initial Simulator Certification.
ML20028H8591990-09-0707 September 1990
Nuclear Quality Audit & Evaluation Review Rept, Sequoyah Nuclear Plant Look Back Review of Cable Issues.
ML20136J0431990-06-30030 June 1990
Criticality Analysis of Sequoyah Units 1 & 2 Fresh Fuel Racks
ML20043B6061990-05-11011 May 1990
Diesel Generator Voltage Response Improvement Rept.
ML20006E5771990-02-0505 February 1990
Rev 1 to Sequoyah Units 1 & 2 Spent Fuel Storage Rack Criticality Analysis.
ML20246D5351989-02-28028 February 1989
Steam Generator Tubing Insp Results
ML20247H1301988-11-30030 November 1988
Rev 0 to Structural Analysis & Evaluation of Sequoyah Reactor Coolant Pump Support Columns
ML20236D1951988-11-18018 November 1988
HVAC Damping Values
ML20134H6801988-09-0202 September 1988
Technical Evaluation of Procurement of Matls & Svcs
ML20245B4181988-08-17017 August 1988
Investigation Rept,Design & Operation of Sampling Sys for Analysis of High Purity Water
ML20151Q2691988-08-0101 August 1988
Final Rept on IE Bulletin 79-14 for Tva,Sequoyah Nuclear Plant Unit 1 & Common Piping
ML20155J5721988-07-31031 July 1988
Assessment of Structural Adequacy of Concrete Foundation Cells for Emergency Raw Cooling Water Pumping Station & Access Roadway
ML20207F6231988-07-0505 July 1988
Evaluation of Effects of Postulated Pipe Failures Outside of Containment for Sequayah Nuclear Plant,Units 1 & 2
ML20207B6301988-06-27027 June 1988
Engineering Assurance Oversight Review Rept,Sequoyah Nuclear Plant - Unit 1,Design Baseline & Verification Program
ML20147G9961988-03-31031 March 1988
Review of Operational Readiness Corrective Actions. Related Documentation Encl
ML20147H6331988-02-29029 February 1988
Plant,Diesel Generator Evaluation Rept
ML20147G7861988-02-25025 February 1988
Task Rept on Development of Seismic Acceleration Response Spectra for Diesel Generator Bldg of Sequoyah Nuclear Plant, Part 1:Design Basis SSE Input
ML20147G8041988-02-25025 February 1988
Task Rept on Development of Seismic Acceleration Response Spectra for Diesel Generator Bldg of Sequoyah Nuclear Plant, Part 2:Site-Specific OBE & SSE Inputs
ML20234F2111988-01-0505 January 1988
Rept of Sequoyah Readiness Review
ML20147F0581987-12-0202 December 1987
Non-linear Time History Seismic Response Analyses for ERCW Cell, Task Rept
ML20236B3481987-10-15015 October 1987
Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 207.4(B), Deviation Documentation:Caq Documentation
ML20236B3511987-10-14014 October 1987
Rev 0 to TVA Employee Concerns Special Program Sequoyah Element Rept 232.8(B), Piping & Valve Design:Criteria for Min Pipe Wall Thickness
ML20236B3541987-10-14014 October 1987
Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 235.2(B), Electrical Safety:Exposed 480 Volt Bus at Panel Top
ML20236B3441987-10-14014 October 1987
Rev 0 to TVA Employee Concerns Special Program Sequoyah Element Rept 204.9(B), Use of Reverse Prints
ML20236B3581987-10-14014 October 1987
Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 241.4(B), Cable Termination & Splices:Amphenol Connector
ML20236Q2011987-10-0101 October 1987
Temp Measurement Rept for Long-Term Current Test on Littlefuse,Flas-5,5 Amp Fuses
1999-08-02
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20212J6311999-10-0101 October 1999
SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1
ML20217G3721999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With
ML20212F0831999-09-23023 September 1999
Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval
ML20212F4761999-09-23023 September 1999
Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively
ML20212C4761999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With
ML20210L4361999-08-0202 August 1999
Cycle 9 12-Month SG Insp Rept
ML20216E3781999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With
ML20210L4451999-07-31031 July 1999
Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept
ML20210G6631999-07-28028 July 1999
Cycle 9 90-Day ISI Summary Rept
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML20209H3831999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With
ML20211F9031999-06-30030 June 1999
Cycle 9 Refueling Outage
ML20196J8521999-06-28028 June 1999
Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i)
ML20195K2951999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With
ML20206Q8951999-05-0505 May 1999
Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10
ML20206R5031999-04-30030 April 1999
Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With
ML20205P9811999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With
ML20204C3111999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With
ML20205B6631999-02-28028 February 1999
Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys
ML20203H7381999-02-18018 February 1999
Safety Evaluation of Topical Rept BAW-2328, Blended U Lead Test Assembly Design Rept. Rept Acceptable Subj to Listed Conditions
ML20211A2021999-01-31031 January 1999
Non-proprietary TR WCAP-15129, Depth-Based SG Tube Repair Criteria for Axial PWSCC Dented TSP Intersections
ML20198S7301998-12-31031 December 1998
Cycle 10 Voltage-Based Repair Criteria 90-Day Rept
ML20199G3641998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With
ML20197J5621998-12-0303 December 1998
Unit 1 Cycle 9 90-Day ISI Summary Rept
ML20197K1161998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With
ML20195F8061998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Sequoyah Nuclear Plant.With
ML20154H6091998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With
ML20154H6251998-09-17017 September 1998
Rev 0 to Sequoyah Nuclear Plant Unit 1 Cycle 10 Colr
ML20153B0881998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for Sequoyah Nuclear Plant.With
ML20239A0631998-08-27027 August 1998
SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2
ML20236Y2091998-08-0707 August 1998
Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08
ML20237B5221998-07-31031 July 1998
Monthly Operating Repts for July 1998 for Snp
ML20237A4411998-07-31031 July 1998
Blended Uranium Lead Test Assembly Design Rept
ML20236P6441998-07-10010 July 1998
LER 98-S01-00:on 980610,failure of Safeguard Sys Occurred for Which Compensatory Measures Were Not Satisfied within Required Time Period.Caused by Inadequate Security Procedure.Licensee Revised Procedure MI-134
ML20236R0051998-06-30030 June 1998
Monthly Operating Repts for June 1998 for Sequoyah Nuclear Plant
ML20249A8981998-05-31031 May 1998
Monthly Operating Repts for May 1998 for Sequoyah Nuclear Plant,Units 1 & 2
ML20247L5141998-04-30030 April 1998
Monthly Operating Repts for Apr 1998 for Sequoyah Nuclear Plant
ML20217K4471998-04-27027 April 1998
Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05
ML20217E2221998-03-31031 March 1998
Monthly Operating Repts for Mar 1998 for Sequoyah Nuclear Plant
ML20248L2611998-02-28028 February 1998
Monthly Operating Repts for Sequoyah Nuclear Plant,Units 1 & 2
ML20199J2571998-01-31031 January 1998
Cycle 9 Voltage-Based Repair Criteria 90-Day Rept
ML20202J7911998-01-31031 January 1998
Monthly Operating Repts for Jan 1997 for Sequoyah Nuclear Plant,Units 1 & 2
ML20199J2441998-01-29029 January 1998
Snp Unit 2 Cycle Refueling Outage Oct 1997
ML20199F8531998-01-13013 January 1998
ASME Section XI Inservice Insp Summary Rept for Snp Unit 2 Refueling Outage Cycle 8
ML20199A2931997-12-31031 December 1997
Revised Monthly Operating Rept for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2
ML20198M1481997-12-31031 December 1997
Monthly Operating Repts for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2
ML20197J1011997-11-30030 November 1997
Monthly Operating Repts for Nov 1997 for Sequoyah Nuclear Plant,Units 1 & 2
ML20199C2951997-11-13013 November 1997
LER 97-S01-00:on 971017,vandalism of Electrical Cables Was Observed.Caused by Vandalism.Repaired Damaged Cables, Interviewed Personnel Having Potential for Being in Area at Time Damage Occurred & Walkdowns
ML20199C7201997-10-31031 October 1997
Monthly Operating Repts for Oct 1997 for Sequoyah Nuclear Plant
L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997
SG Secondary Side Loose Object Safety Evaluation
1999-09-30
[Table view] |
Text
- - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _
(
l l
TENNESSEE VALLEY AUTHORITY l
WATTS BAR NUCLEAR PLANT EMPLOYEE CONCERNS TASK GROUP OTHER SITES CEG 1
Element
Title:
Surveillance, Frisking, and Outage Work SWEC Concerns: A02851101010-001
-002
-003 A02851216011-001 Source Document: NRC Inspection Report 50-327, 328/85-32 and 85-38 Report Number: SWEC-SQN--45 and SWEC-SQN-51 Evaluator: 80 J. J.,l(night:.y Date Reviewed by: ! gy (0/3/f(,
A. G. Deb &ge dat6 Approved by: e Ibr /8/2 /([u.
R. C. Sauf ' Oafe 1271T ~
~ 8612090773 861120 7 PDR ADOCK 0500 P
Report SWEC-SQN-45 and SWEC-SQN-51 Surveillance, Frisking, and Outage Work I
I. Introduction During the plant operations inspection of September 6 through October 5, 1985, the Nuclear Regulatory Commission (NRC) identified one violation, one concern related to a previous violation, and one inspector followup item which were included in the Stone & Webster Engineering Corporation (SWEC) systematic analysis:
A. A02851101010-001, SI Test Failure to Switch to Test Position; B. 402851101010-002, Frisking Noncompliance; and C. A02851101010-003, Outage Work Deficiencies, Housekeeping.
During an inspection of November 18-21, 1985 the NRC inspector identified an additional example of frisking noncompliance which was included in the SWEC systematic analysis.
D. A02851216011-001, Frisking Noncompliance - Repeat Violation Employee Concerns Task Group (ECTG) verification for this repeat frisking violation is included with IB above.
Information on the background, the corrective actions taken, the verification methodology and analysis the completion status, and any pertinent references for these items is included in this report.
II. Verification of SWEC Items A. A02851101010-OO1, SI Test Failure to Switch to Test position
- 1. Background The NRC inspection determined that during a test of the Control Room Air Intake Chlorine Detection System on August 27, 1985, an SQN technician failed to place switch HS-43-2058 in the test position before introducing chlorine fumes into the system as required by Surveillance Instruction SI-240, Revision 11 "Funtional Test of Control Room Air Intake Chlorine Detection System." This resulted in an engineered safety future actuation (control room isolation) when the chlorine fumes were injected into the system. This employee had not been in the maintenance area when a memorandum on following instructions had been issued on or about July 22, 1985, in response to IFI 327, 328/85-26-07.
page 1 of 5
- 2. Corrective Actions Taken SQN attributed this violation to personnel error and took appropriate disciplinary action against the employee. The control room ventilation system was returned to normal immediately in accordance with System Operating Instruction (SOI)-30.1, Revision 14 " Control Building and Control Room Heating, Air Conditioning and Ventilation System" and the need to follow established procedures was re-emphasized to the instrument maintenance personnel (reference B).
- 3. Verification Methodology The SWEC concern. identified for Employee Concerns Task Group (ECTG) verification was stated as follows:
RIMS # Issue RIMS Item A02851101010 During Surv. Testing RIMS-OO1 the Technician Failed to place switch in the test position. Result:
Engineered Safety Featured Actuation / Control Room Isolation.
ECTG reviewed the Sequoyah 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. The NRC found the SQN response to be acceptable and closed the violation in Report 86-15, dated April 4, 1986.
l l 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 SWEC item is closed.
i B. A02851101010-002 and A02851216011, Frisking Noncompliance
1. Background
The NRC inspectors observed (References A and F) further i
examples of noncompliance to Radiological Control Instruction i RCI-1, Revision 27 " Radiological Hygiene Control" as cited in a previous violation (85-26-03), dated September 6, 1985. In
' these examples, employees were observed exiting regulated areas l without performing adequate hand and feet frisking. Additional l Page 2 of 5 l
l L
a violations were not issued as TVA was in the process of implementing corrective action for the earlier violation. NRC requested (Reference F) a supplemental response detailing how full compliance will be achieved.
- 2. Corrective Actions Taken TVA stated (Reference H) that a health physics technician would be assigned to the maintenance section to provide additional training and assure awareness of Health Physics procedures and practices. In their supplemental response (Reference G), SQN outlined corrective actions including (1) signs at main egress stations detailing proper frisking techniques: (2) clocks at these stations to help personnel comply with frisking time requirements; (3) disciplinary action for violators; and (4) quality assurance staff weekly surveillances for personnel dosimetry and frisking compliance.
- 3. Verification Methodology The SWEC concerns identified for ECTG verification was stated as follows:
RIMS # Issue RIMS Item A02851101010 Noncompliance to HP RIMS-OO2 Frisking Procedures Training Program to be implemented. Frisked feet but not hands per procedure.
A02851216011 Repeat violation RIMS-001 concerning personnel frisking noted.
Additional response with corrective actions required.
ECTG reviewed the Sequoyah Compliance Licensing files for internal and external correspondence related to the issue. This review of the pertinent documentation formed the basis for this verification activity.
- 4. Verification Analysis The ECTG review found that the NRC violation was closed in NRC inspection Report 86-15 dated April 4, 1986. NRC noted at this time that they reviewed the SQN quality assurance audits of surveillances for personnel dosimetry and frisking. It was noted that SQN audits for strict compliance to Health Physics practices had improved and the inspector observed an increased awareness among plant personnel of proper placement of dosimetry and frisking techniques.
Page 3 of 5
~ ,
- 5. Completion Status
' Based on the SQN corrective actions, compliance with L requirements, and NRC closure of the item, no further action is required. This item is closed.
- C. A02851191919-003, Outage Work Deficiencies
! 1. Background
}' The NRC inspector noted several housekeeping discrepancies during a partial walkdown of the accessible portions of the Component Cooling Water System on Units 1 and 2; General l housekeeping in several areas was marginal; new piping segments j were attached to existing fire protection piping using masking iI tape; valve labels and location identifiers were not clear and conduit was degraded (no details available). Followup of plant-h housekeeping under SQA-66, Revision 9 " Plant Housekeeping," and F Operations Section Letter - Administrative (OSLA)-99 " Auxiliary b Unit Operator Duties" (dated February 27, 1986) was to be taken under IFI 85-32-02.
4
- 2. Corrective Actions Taken
, During the inspection SQN attributed these discrepancies to outage activities, and stated that corrective action of such discrepancies should occur during the routine, monthly 3
housekeeping tours performed under SQA-66. Identification of
/t such discrepancies is to be done by Auxiliary Unit Operators in accordance with OSLA-99. .
- 3. Verification Methodology The SWEC concern identified for ECTG verification was stated as follows:
k- RIMS # Issue RIMS Item e
A02851101010 Various Discrepancies RIMS-003 f Attributed to Outage
- Work-Poor Housekeeping, h conduit Degradation, Valve Mislabeling.
{
1 t ECTG reviewed the Sequoyah 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.
l
- 4. Verification Analysis J The ECTG review of the pertinent documentation indicated that the NRC has not closed this item. The housekeeping problem was k identified as an NRC violation (85-45-09) in February 1986 f (Reference C). SQN's response (Reference D) stated that cleanup Page 4 of 5 A
activities had not been completed because of the continuing SQN plant outage; that housekeeping would continue and a complete plant cleanup program would be completed before start up. This response was found acceptable to the NRC in Reference E.
- 5. Completion Status SQN's planned corrective action for this issue was accepted by the NRC. Following corrective action implementation and NRC closure, this SWEC concern can be closed.
III. References A. NRC Inspection Report Numbers 50-327/85-32 and 50-328/85-32, dated October 30, 1985, from D. M. Verrelli to H. G. Parris B. TVA Memorandum "Sequoyah Nuclear Plant Units 1 and 2-NRC-OIE Region II Inspection Report 50-327/85-32 and 50-328/85 Response to Violations," dated November 26, 1985, from R. H. Shell to J. N. Grace C. NRC Inspection Report Numbers 50-327/85-45 and 50-328/85-45, dated February 18, 1986, from J. A. Olshinski to S. A. White D. TVA Memorandum, "Sequoyah Nuclear Plant Units 1 and 2 - NRC-OIE Region II Inspection Report 50-327/85-45 and 50-328/85 Response to Violations," dated March 20, 1986, from R. Gridley to J. N. Grace E. NRC Memorandum, "NRC Inspection Report Numbers 50-237/85-45 and 50-328/85-45," dated May 28, 1986, from J. A. Olshinski to S. A.
White F. NRC Inspection Report Numbers 50-327/85-45 and 50-328/85-38, dated December 12, 1985, from D. M. Verrelli to H. G. Parris G. TVA Memorandum, " Supplemental Response - NRC-OIE Inspection Report Numbers 50-327/85-26 and 50-328/85-26," dated January 3, 1986, from R. Gridley to J. N. Grace H. TVA Memorandum, "Sequoyah Nuclear Plant Units 1 and 2 - NRC-OIE Region II Inspection Report 50-327/85-26 and 50-328/85-26," dated October 7, 1985, from R. H. Shell to J. N. Grace Page 5 of 5
s TVA EMPLOYEE CONCERNS REPORT NUMBER: SWEC-SQN-45 end 51 SPECIAL PROGRAN REPORT TYPE: Sequoyah Nuclear Plant Element REVISION NUMBER: 0 TITLE: Surveillance, Frisking, and Outage Work 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 A02851101010-001, -002 and A02851216011-001 were closed by NRC. Corrective action for concern A02851101010-003 is in progress.
PREPARATION PREPARED BY: I Y '
eifikkip SIGNATURE DATE REVIEWS PEER:
W h. //-//- S I.,
1 SIGNATURE DATE 1 A$Y ' '
/ // E SIGNATURE DATE CONCURRENCES CEG-H: & Mln/tL SRP: 0 mptb / Yd$ // 4M SIGNATURE DATE
[ SIGNATURf [ DATE APPROVED BY-h 1/ A ECSP 'MANAd ER l $~h DATE N/A MANAGER OF NUCLEAR POWER DATE CONCURRENCE (FINAL REPORT ONLY)
- SRP Secretary's signature denotes SRP concurrences are in files.
2242T