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{{#Wiki_filter: | {{#Wiki_filter:- ______ _ | ||
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* | |||
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,. 3 ; | |||
0 | |||
OCT 2 01933 | |||
Docket Nos.: 50-327 and 50-328 | |||
License Nos. DPR-77 and DPR-79 | |||
/ Tennessee Valley Authority | |||
/ ATTN: Mr. S. A. White | |||
Senior Vice President, | |||
Nuclear Power | |||
6N 38A Lookout Place | |||
1101 Market Square | |||
j Chattanooga, TN 37402-2801 | |||
Gentlemen: | |||
SUBJECT: NOTICE OF VIOLATION | |||
(NRC INSPECTION REPORT NOS. 50-327/88-29 AND 50-328/88-29) | |||
This refers to Nuclear Regulatory Commission (NRC) special announced team | |||
inspection conducted by K. Jenison on June 20, 1988 through July 8, 1988. The | |||
inspectior. included a review of the activities associated with the startup of | |||
Sequoyah Unit 1 and the Sequoyah restart program matrix. At the conclusion of | |||
the inspection, the findings were discussed with those members of your staff | |||
identified in the enclosed inspection report. | |||
The purpose of this inspection was to determine if adequate implementation of | |||
corrective actions had occurred to support Unit I startup. These corrective | |||
actions included TVA Nuclear Perfora nce Plan implementation and evaluation of | |||
equivalent Unit 2 startup items on Unit 1. This determination was based on a | |||
sample of the programma*.ic corr'ective actions that pertained to the containment | |||
spray system. The results cf this inspection were used to evaluate the need | |||
for additional NRC activity in specifically identified areas. | |||
This inspection was composed of design and as-constructed aspects. Contact was | |||
maintained between inspectors in each area such that their respective efforts | |||
and inspection findings were coordinated. The design portions consisted of a | |||
review of portions of the containment spray system design, design bases and | |||
design requirements. The as-constructed portion consisted of an in plant | |||
review in the mechanical, electrical, civil, structural, and instrumentation | |||
and control disciplines in order to verify that the containment spray system as | |||
currently constructed and installed is in accordance with the licensed design | |||
basis, system design specifications, applicable drawings, system modifications | |||
and temporary alterations. In addition, the operational capability of the | |||
containment spray system was evaluated by reviewing the system operating | |||
instructions and procedures, surveillance and testing requirements, corrective | |||
and preventive maintenance activities, emergency operating instructions and | |||
operator training. The inspection team evaluated, on a sampling basis, | |||
8811030366 001020 | |||
PDR ADOCK 05000327 | |||
O PNU 1 | |||
1 | |||
_ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ | |||
Y WI | |||
- _ _ _ _ _ _ _ | |||
_. | |||
~ | |||
* | |||
; .' OCT 2 01938 | |||
Tennessee Valley Authority 2 | |||
portions of the TVA Nuclear Performance Plan functional corrective action | |||
areas that were not addressed for Unit 1 in other inspections. The areas not | |||
addressed for Unit 1 in other inspections were established by a review of | |||
those NRC inspections conducted since the shutdown of Sequoyah Units 1 and 2 | |||
(August 1985). | |||
The inspection findings indicate Uias certain activities appeared to violate | |||
NRC requirements. The identified violations involved aissing system design | |||
basis calculations, procedural noncompliances associated with electrical work, | |||
structural walkdown discrepancies, and procedure inadequacies in the areas of | |||
ASME Section XI testing and weld evaluations. The violatuns, references to | |||
pertinent requirements, and elements to be included in you, response are | |||
described in the enclosed Notice of Violation. | |||
As discussed during the exit, several of the above violations have additional | |||
corrective actions associated with them in order to ensure adequate resolution | |||
of the issue. These additional corrective actions are as follows: | |||
Violation 327, 328/88-29-01, Design Basis Calculation Discrepancies, has | |||
associated with it additional corrective actions identified as Unresolved | |||
Item 327,328/88-29-06a through s. Adequate corrective action for .his | |||
violation should include resolution of these issues and a 100% Engineering | |||
Assurance review of the results. | |||
Violation 327,328/88-29-02, Structural Walkdown Discrepancies, Ms | |||
associated with it additional issues which require unique, generic a,d | |||
programmatic review. This review should also include a TVA Quality | |||
Assurance review of the TVA pre-SSQE walkdown discrepancies and the | |||
applicability of those discrepancies to other components. | |||
Violation 327,328/88-29-03, Maintenance of Safety-Related Electrical | |||
Equipment, has associated with it additional issues which require unique, | |||
generic and programmatic review. This review should also include a TVA | |||
Quality Assurance review of the TVA pre-SSQE walkdown discrepancies and | |||
the applicability of those discrepancies to other components. | |||
In addition to the above violations, several commitments were made during the | |||
exit meeting on July 8, 1988, conducted for this inspection. These commitments | |||
were: | |||
To test the containment spray pump flow characteristics using a multiple | |||
point test prior to the startup cf Unit 3. | |||
To test the ESF pump valve logic performance as demonstrated in surveil- | |||
# lance instruction 68 prior to the startup of Unit 1. | |||
To complete licensee actions associated with establishing the 143 psid | |||
pressure required to ensure 4750 gpm f rom the containment spray pumps | |||
prior to the startup of Unit 1. | |||
To determine actual containment spray anu RHR heat exchanger differential | |||
pressure in order to resolve restart test functions 72-003 and 72-018 | |||
prior to the startup of Unit 1. | |||
_ - - - - - - - - - - - - - - - - - - - - - -- A | |||
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . | |||
' | |||
' | |||
; | |||
,. | |||
OCT t 31988 | |||
Tennessee Valley Authority 3 | |||
To include in the next scheduled update of the containment spray training | |||
lesson p'ans, information on the manual suction source swapover of the , | |||
containment spray system and the interlocks associated with the system. | |||
Based on a review of the containment spray system, there appears to be adequate | |||
' | |||
program implementation in the following areas to support Unit 1 startup without | |||
i further NRC inspection: i | |||
Design Basis Verification Program , | |||
; TVA as-constructed walkdowns ; | |||
Drawing Control Program | |||
' | |||
Inplant Configuration Control and System Alignment | |||
Surveillance Instructions | |||
ASME Section XI | |||
Restart Test and Functional Performance Program | |||
Cricical Calculation Regeneration Program | |||
De*,ign Change and Modifications Program | |||
Caole Routing and Cable Leading | |||
Equipment Qualification and Seismic Programs | |||
Preoperational Test Program | |||
Employee Concerns | |||
Condition Adverse to Quality Reports including the Quality Assurance | |||
audit process | |||
Potential Reportable Occurrences and Licensee Event Reports | |||
4 Nuclear Experience Review | |||
Instrument Line Slope | |||
System Operating and Emergency Operating Instructions | |||
, | |||
Alternate and Rigorous Support Analysis | |||
1 Maintenance (including trending, material control, preventive maintenance , | |||
and housekeeping) ; | |||
Operability Lookback : | |||
i | |||
Fi:tform Thermal Growth | |||
Cable Tray Supports | |||
Welding (including pipe, structural, and civil) i | |||
1 Operator Training ! | |||
i | |||
} | |||
Nuclear Performance Plan implementation requiring additional NRC review I | |||
' | |||
is as follows: | |||
l | |||
l | |||
Critical Calculations Regeneration Program (as part : | |||
i of violation 327, 328/88-29-01 review) ( | |||
Appendix R ! | |||
' | |||
Electrical System SER related issues | |||
Functional test observation of pump flow and component | |||
, logic | |||
' 10 CFR 50 Appendix J testing ! | |||
! | |||
: | |||
I | |||
- | |||
l | |||
! ! | |||
1 | |||
i | |||
l | |||
, | |||
! [ | |||
i ! | |||
I _-____-_--_ __. .. | |||
__ . | |||
, | |||
. | |||
, | |||
Tennessee Valley Authority 4 | |||
In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2, | |||
Title 10. Code of Federal Regulations, a copy of this letter, its enclosures, | |||
and any reply will be placed in the NRC's Public Document Room. | |||
The responses directed by this letter and its enclosures are nct subjected to | |||
the clearance procedures of the Office of Management and Budget a> required by | |||
the Paperwork Reduction Act of 1980, PL 96-511. | |||
Should you have any questions concerning this letter, please contact us. | |||
Sincerely, | |||
{) Ah w0 S& * | |||
Steven D. Richardson, Director | |||
TVA Projects Division | |||
Office of Special Projects | |||
Enclosures: | |||
1. Notice of Violation | |||
2. NRC Inspection Report | |||
cc w/encis: | |||
/J. L. Kirkebo, Vice President | |||
Nuclear Engineering | |||
vJ. L. LaPoint, Acting Site Director | |||
Sequoyah Nuclear Plant | |||
4 . L. Gridley, Director | |||
f Nuclear Safety and Licensing | |||
'M. R. Harding, Site Licensing | |||
Manager | |||
/TVA Representative, Rockville | |||
Office | |||
sState of Tennessee | |||
General Counsel, TVA | |||
bec w/encis: | |||
-J. G. Partlow, OSP | |||
S. C. Black, OSP | |||
B. D. Liaw, OSP | |||
F. R. McCoy, OSP | |||
,K. P. Barr, OSP | |||
.L. J. Watson, OSP | |||
',J. B. Brady, OSP | |||
i R. E. Shewmaker, OSP | |||
i '/J. Rutberg, OGC | |||
' | |||
NRC Resident Inspector - | |||
NRC Occument Control Desk 7' | |||
0 OSP/RI! OSP/RIE OSP:TVATP:E 0$il AD P 050 :D | |||
)IIg g) )j RShewmaker,' BD la I SRichardson | |||
j | |||
du tm that <on .Jgu~ f,4 | |||
- | |||
10/l;/83 10/' a # 8 10/pj/88 | |||
10/3 /88 10/f/88 10/f/88 | |||
i _ | |||
}} | }} |
Latest revision as of 21:21, 16 December 2020
ML20195C761 | |
Person / Time | |
---|---|
Site: | Sequoyah ![]() |
Issue date: | 10/20/1988 |
From: | Richardson S NRC OFFICE OF SPECIAL PROJECTS |
To: | White S TENNESSEE VALLEY AUTHORITY |
Shared Package | |
ML20195C765 | List: |
References | |
NUDOCS 8811030366 | |
Download: ML20195C761 (4) | |
See also: IR 05000327/1988029
Text
- ______ _
'
,. 3 ;
0
OCT 2 01933
Docket Nos.: 50-327 and 50-328
License Nos. DPR-77 and DPR-79
/ Tennessee Valley Authority
/ ATTN: Mr. S. A. White
Senior Vice President,
Nuclear Power
6N 38A Lookout Place
1101 Market Square
j Chattanooga, TN 37402-2801
Gentlemen:
SUBJECT: NOTICE OF VIOLATION
(NRC INSPECTION REPORT NOS. 50-327/88-29 AND 50-328/88-29)
This refers to Nuclear Regulatory Commission (NRC) special announced team
inspection conducted by K. Jenison on June 20, 1988 through July 8, 1988. The
inspectior. included a review of the activities associated with the startup of
Sequoyah Unit 1 and the Sequoyah restart program matrix. At the conclusion of
the inspection, the findings were discussed with those members of your staff
identified in the enclosed inspection report.
The purpose of this inspection was to determine if adequate implementation of
corrective actions had occurred to support Unit I startup. These corrective
actions included TVA Nuclear Perfora nce Plan implementation and evaluation of
equivalent Unit 2 startup items on Unit 1. This determination was based on a
sample of the programma*.ic corr'ective actions that pertained to the containment
spray system. The results cf this inspection were used to evaluate the need
for additional NRC activity in specifically identified areas.
This inspection was composed of design and as-constructed aspects. Contact was
maintained between inspectors in each area such that their respective efforts
and inspection findings were coordinated. The design portions consisted of a
review of portions of the containment spray system design, design bases and
design requirements. The as-constructed portion consisted of an in plant
review in the mechanical, electrical, civil, structural, and instrumentation
and control disciplines in order to verify that the containment spray system as
currently constructed and installed is in accordance with the licensed design
basis, system design specifications, applicable drawings, system modifications
and temporary alterations. In addition, the operational capability of the
containment spray system was evaluated by reviewing the system operating
instructions and procedures, surveillance and testing requirements, corrective
and preventive maintenance activities, emergency operating instructions and
operator training. The inspection team evaluated, on a sampling basis,
8811030366 001020
PDR ADOCK 05000327
O PNU 1
1
_ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _
Y WI
- _ _ _ _ _ _ _
_.
~
- .' OCT 2 01938
Tennessee Valley Authority 2
portions of the TVA Nuclear Performance Plan functional corrective action
areas that were not addressed for Unit 1 in other inspections. The areas not
addressed for Unit 1 in other inspections were established by a review of
those NRC inspections conducted since the shutdown of Sequoyah Units 1 and 2
(August 1985).
The inspection findings indicate Uias certain activities appeared to violate
NRC requirements. The identified violations involved aissing system design
basis calculations, procedural noncompliances associated with electrical work,
structural walkdown discrepancies, and procedure inadequacies in the areas of
ASME Section XI testing and weld evaluations. The violatuns, references to
pertinent requirements, and elements to be included in you, response are
described in the enclosed Notice of Violation.
As discussed during the exit, several of the above violations have additional
corrective actions associated with them in order to ensure adequate resolution
of the issue. These additional corrective actions are as follows:
Violation 327, 328/88-29-01, Design Basis Calculation Discrepancies, has
associated with it additional corrective actions identified as Unresolved
Item 327,328/88-29-06a through s. Adequate corrective action for .his
violation should include resolution of these issues and a 100% Engineering
Assurance review of the results.
Violation 327,328/88-29-02, Structural Walkdown Discrepancies, Ms
associated with it additional issues which require unique, generic a,d
programmatic review. This review should also include a TVA Quality
Assurance review of the TVA pre-SSQE walkdown discrepancies and the
applicability of those discrepancies to other components.
Violation 327,328/88-29-03, Maintenance of Safety-Related Electrical
Equipment, has associated with it additional issues which require unique,
generic and programmatic review. This review should also include a TVA
Quality Assurance review of the TVA pre-SSQE walkdown discrepancies and
the applicability of those discrepancies to other components.
In addition to the above violations, several commitments were made during the
exit meeting on July 8, 1988, conducted for this inspection. These commitments
were:
To test the containment spray pump flow characteristics using a multiple
point test prior to the startup cf Unit 3.
To test the ESF pump valve logic performance as demonstrated in surveil-
- lance instruction 68 prior to the startup of Unit 1.
To complete licensee actions associated with establishing the 143 psid
pressure required to ensure 4750 gpm f rom the containment spray pumps
prior to the startup of Unit 1.
To determine actual containment spray anu RHR heat exchanger differential
pressure in order to resolve restart test functions72-003 and 72-018
prior to the startup of Unit 1.
_ - - - - - - - - - - - - - - - - - - - - - -- A
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
'
'
,.
OCT t 31988
Tennessee Valley Authority 3
To include in the next scheduled update of the containment spray training
lesson p'ans, information on the manual suction source swapover of the ,
containment spray system and the interlocks associated with the system.
Based on a review of the containment spray system, there appears to be adequate
'
program implementation in the following areas to support Unit 1 startup without
i further NRC inspection: i
Design Basis Verification Program ,
- TVA as-constructed walkdowns ;
Drawing Control Program
'
Inplant Configuration Control and System Alignment
Surveillance Instructions
Restart Test and Functional Performance Program
Cricical Calculation Regeneration Program
De*,ign Change and Modifications Program
Caole Routing and Cable Leading
Equipment Qualification and Seismic Programs
Preoperational Test Program
Employee Concerns
Condition Adverse to Quality Reports including the Quality Assurance
audit process
Potential Reportable Occurrences and Licensee Event Reports
4 Nuclear Experience Review
Instrument Line Slope
System Operating and Emergency Operating Instructions
,
Alternate and Rigorous Support Analysis
1 Maintenance (including trending, material control, preventive maintenance ,
and housekeeping) ;
Operability Lookback :
i
Fi:tform Thermal Growth
Cable Tray Supports
Welding (including pipe, structural, and civil) i
1 Operator Training !
i
}
Nuclear Performance Plan implementation requiring additional NRC review I
'
is as follows:
l
l
Critical Calculations Regeneration Program (as part :
i of violation 327, 328/88-29-01 review) (
Appendix R !
'
Electrical System SER related issues
Functional test observation of pump flow and component
, logic
' 10 CFR 50 Appendix J testing !
!
I
-
l
! !
1
i
l
,
! [
i !
I _-____-_--_ __. ..
__ .
,
.
,
Tennessee Valley Authority 4
In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2,
Title 10. Code of Federal Regulations, a copy of this letter, its enclosures,
and any reply will be placed in the NRC's Public Document Room.
The responses directed by this letter and its enclosures are nct subjected to
the clearance procedures of the Office of Management and Budget a> required by
the Paperwork Reduction Act of 1980, PL 96-511.
Should you have any questions concerning this letter, please contact us.
Sincerely,
{) Ah w0 S& *
Steven D. Richardson, Director
TVA Projects Division
Office of Special Projects
Enclosures:
1. Notice of Violation
2. NRC Inspection Report
cc w/encis:
/J. L. Kirkebo, Vice President
Nuclear Engineering
vJ. L. LaPoint, Acting Site Director
Sequoyah Nuclear Plant
4 . L. Gridley, Director
f Nuclear Safety and Licensing
'M. R. Harding, Site Licensing
Manager
/TVA Representative, Rockville
Office
sState of Tennessee
General Counsel, TVA
bec w/encis:
-J. G. Partlow, OSP
S. C. Black, OSP
B. D. Liaw, OSP
F. R. McCoy, OSP
,K. P. Barr, OSP
.L. J. Watson, OSP
',J. B. Brady, OSP
i R. E. Shewmaker, OSP
i '/J. Rutberg, OGC
'
NRC Resident Inspector -
NRC Occument Control Desk 7'
0 OSP/RI! OSP/RIE OSP:TVATP:E 0$il AD P 050 :D
)IIg g) )j RShewmaker,' BD la I SRichardson
j
du tm that <on .Jgu~ f,4
-
10/l;/83 10/' a # 8 10/pj/88
10/3 /88 10/f/88 10/f/88
i _