ML20196D083
| ML20196D083 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/16/1998 |
| From: | Christensen H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Scalice J TENNESSEE VALLEY AUTHORITY |
| References | |
| NUDOCS 9812020153 | |
| Download: ML20196D083 (34) | |
Text
_ _ _ _ ._ . ._ __. . _ . _ _ __
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November 16, 1998 l
Tennessee Valley Authority ATTN: Mr. J. A. Scalice {
i Chief Nuclear Officer and l Executive Vice President 1 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 I
SUBJECT:
INSPECTION PLAN - SEQUOYAH NUCLEAR PLANT
Dear Mr. Scalice:
J On November 2,1998, the NRC staff completed an inspection resource planning meeting.
The staff conducted this review for all operating nuclear power plants in Region 11 to develop an l
integrated inspection plan. We conducted this meeting in lieu of the semiannual Plant '
Performance Review, which the staff has moved to February 1999 because of the agency's shift to an annual Senior Management Meeting cycle.
This letter advises you of our planned inspection effort resulting from the inspection plannmg )
meeting. We have provided it to minimize the resource impact on your staff and to allow for j scheduling conflicts and personnel availability to be resolved before the inspector's arrival l onsite. Enclosure 1 details our inspection ple.n through March 1999. We have provided the l rationale or basis for each inspection outside the core inspection program so that you are aware i of the reason for emphasis in these progra'n areas. Resident inspections are not listed due to their ongoing and continuous nature.
During this scheduling cycle, we will continue to focus some of our discretionary inspection
- j. effort on the resolution of open inspection items. Therefore, we may conduct additional
- inspections, which are not listed on Enclosure 1, to close open inspection items that are ready to be resolved. We will notify you at ! east 3 weeks before the start of these inspecticns.
The NRC's general policy for reactor inspections is that we will announce each inspection, unless announcing the inspection could compromise the objectives of the inspectors.
Therefore, we may not have included some specific inspections on Enclosure 1, such as in the security and radiological protection areas, and these inspections may not be announced.
Enclosure 2 contains a historicallisting of plant issues, called the Plant Issues Matrix (PIM).
The PIM includes only items from inspection reports or other docketed correspondence between the NRC and Sequoyah Nuclear Plant. This material will be placed in the public [ i document room.
l 4 :
9812O20153 981116 l I PDR ADOCK 05000327 G PDR ;
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_ .. _ >_ __ . .__.__ _ _ _ _-_ . _ _ _ _ . . _ _ ~ . ._
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l TVA- 2 We willinform you of any changes to the enclosed inspection plan if you have any questions, ;
please contact Harold Christensen at (404) 562-4530. i l
Sincerely, I l
(Original signed by Harold O. Christensen) !
Harold O. Christensen, Chief j Reactor Projects Branch 6 !
Division of Reactor Projects l
l Docket Nos. 50-327,50-328 ;
Enclosures:
- 1. Inspection Plan ,
- 2. Plant issues Matrix l l
cc w/encls:
Senior Vice President Nuclear Operations Tennessee Valley Authority 6A Lookout Place '
1101 Market Street Chattanooga, TN 37402-2801 Jack A. Bailey, Vice President Engineering and Technical Services Tennessee Valley Authority
~ 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 L
L Masoud Bajestani Site Vice President Sequoyah Nuclear Plant Tennessee Valley Authority
- P. O. Box 2000 Soddy-Daisy, TN 37379
! General Counsel Tennessee Valley Authority ET 10H 400 West Sumrnit Hill Drive Knoxville, TN 37902
]
cc w/encls continued: See page 3 r
. ._ -_. ._...... _ _ _ _ _ _ _ . _. _ ._.___ _ _ ..m- . . . . _
.]
i
'TVA- 3 l
cc w/encis: Continued -
~ Raul R. Baron, General Manager I Nuclear Assurance
' Tennessee Valley Authority l
SM Lookout Place .
1101 Market Street .
Chattanooga, TN 37402-2801 i s
Mark J.~ Burzynski, Manager -
Nuclear Licensing .
j Tennessee Valley Authority i 4X Blue Ridge "
1101 Market Street I Chattanooga,- TN 37402-2801 Pedro Salas, Manager Licensing and Indust y Affairs Sequoyah Nuclear Plant
' Tennessee Valley Authority
{
i P. O. Box 2000 '
Soddy-Daisy, TN 37379 - '
(
J. T. Herron, Plant Manager
{
Sequoyah Nuclear Plant -
. Tennessee Valley Authority
. P. O. Box 2000 Soddy Daisy, TN 37379 Michael H. Mobley, Director Division of Radiological Health TN Dept. of Environment and -
Conservation 3rd Floor, LNC Annex 401 Church Street
' Nashville, TN 37243-1532
' County Executive ,
Hamilton County Courthouse ]
Chattanooga, TN 37402-2801 Li
.i
' Distribution w/encls: I
. L. R..Plisco, Ril .
R. W. Hernan, NRR F. Hebdon, NRR
- W. C. Bearden, Ril !
Distribution w/encls continued: See page 4 '
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L I TVA 4 i i l l Distributien w/encis: Continued i l C. F. Srsith, Ril E. D. Testa, Ril
!- D. H. 7 hompson, Ril
- L. S. Mellen, Ril lT PUBLIC l l NRC Resident inspector, Operations I U. S. Nuclear Regulatory Commission l l
1260 Nuclear Plant Road !
i Spring City, TN 37381 J l.
NRC Resident inspector ,
- j. Sequoyah Nuclear Plant '
U. S. Nuclear Regulatory Commission l 2600 Igou Ferry Road i Soddy-Daisy, TN 37379 l l l
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DATE A1/ b /98 11/ @ /98 11/6 /98 J1//j/98 f W
__11/ 11// L /98 ill /98 COPY? /VES1 NO YES NO YES NO (YE W NO /fES) NO _#EE NO YES NO OMAL RECORD COPY DOCUMENT NAME: G:\sO\lL iTERs\PPRsO.LTR YV f
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SEQUOYAH INSPECTION PLAN INSPECTION TITLE / PROGRAM AREA NUMBER OF PLANNED TYPE OF INSPECTION -
PROCEDURE / INSPECTORS INSPECTION COMMENTS TEMPORARY DATES <
INSTRUCTION IP 81700 PHYSICAL SECURITY PROGRAM 1 11/98 CORE INSPECTION FOR POWER REACTORS
[ PLANT SUPPORT - Sl]
IP 62700 BREAKER OVERHAUL REVIEW 1 12/98 REGIONAL INITIATIVE
[ MAINTENANCE - MNT)
IPs 37550 and ENGINEERING and 1 01/99 CORE INSPECTION and 92903 ENGINEERING FOLLOWUP REGIONAL INITIATIVE
[ ENGINEERING - ENG)
IP 37550 ENGINEERING FOLLOWUP 1 01/99 CORE INSPECTION
[ ENGINEERING - ENG]
IPs 84750 EFFLUENTS AND CHEMISTRY 1 03/99 CORE lNSPECTION and 86750 SOLID RAD WASTE & TRANSP. ;
[ PLANT SUPPORT - PS]
IP 83750 RADIATION PROTECTION 1 04/99 CORE INSPECTION ,
[ PLANT SUPPORT - PS)
Enclosure 1
Date: 11/12/1998 United States Nuclear Regulatory Commission Time: 06:i,.4o3 Pope:1 of 3 mesion il PLANT ISSUE MATRIX SEQOOYAH By Dale Functional Temploie Date Source Aroo ID Type Codes item Descripflon 10/10/1998 1998009 Prt ENG NRC MISC Prt SC The licensee determined that close monitoring of unidentified lookoge was on occeptable compensatory measure to stortup and operate Unit I for one opencru g cycle with dried boron on the exterior of the pressurizer.
M M 2A Tec 10/10/1998 1998009 Prt MAINT NRC POS Prt2B f&antenance personnel contributed to the overall success of the Unit 1 Cycle 9 refueling outage by implementing seved significont plant modificohons and completing a well planned outage schedule.
Tec 10/10/1998 1998009 Frt MAINT NRC POS Prt 2B Corrective octions following the failure of a Weshnghouse Type DS-532 480 Voc circuit brecker have brought significant g improvemerits to the Type DS Brecker maintenance program.
Tec 10/10/1998 1998009 Prt MAINT NRC POS Prt 2B The licensee's implementation of Steam Generator and inservice Inspection programs were thorough and done in a g *. g. very professional manner. The steam generator eddy current testing program expanded the state-of-the-crt by implementing a depth-sizing procedure for Primary Water Stress Corrosion Crocking.
Tec 10/10/1998 1998009 Prt OPS Ucensee NEG Prt 1 A Operators overtooded the I A-A EDG for less than 30 seconds when they failed to use oil available instrumentation. The g engineering evoluotion of the EDG overlood event concluded that the short durotion overlood was insignificant. .
Tec 10/10/1998 1998009 Prt OPS NRC NEG Prt 1 A A non-conservative operator oction was observed when a heater drain pump was operated in excess of the maximum g g allowed running current for 40 minutes.
Tec 10/10/1098 1998009 Pri: OPS NRC POS Prt 1 A Operational performance donng the Unit I plant shutdown, outoge, reduced inventory operation and startup was 5,c. $,c.
good and contributed to o successful 29 day refueling outage.
Tec item Type (Compliance, Followup,Other). From 02/22/1998 To 08/28/1999 Ehclosure 2
. United States Nuclear Regulatory Commission Dd.: un,2nm rim.:06:i :o3
- oion il PLANT ISSUE MATRIX Pooe: 2 d 3 SHbG0YAH By Dde Functional Tempide Dde Souce Area ' ID Type Codes l'em Description 10/10/1998 1998009 Prt PLTSUP ' NRC POS Prt IC Radioiogical controls during the UIC9 outage were effective os evidenced by a record low totd dose for Unit 1 of 200 g '. g* rem. Moxirma n indMdud radiction exposures were controlled to levels which were we8 within the Icensee's d 4 6;iviive Emit and the regulatory 8mits for occupationd dose specified in 10 CFR 20.1201(c). The Licensee was Ter: generoly successfulin meethg established ALARA goals.
10/10/1998 1998009 Prt PLTSUP NRC POS Prt 1C The licensee had implemented on effective shutdown chemistry control plon and closely monitored pnmary coolant g g chemistry dunng the shutdown for the Unit I refueling outage.
Tee.~
10/10/1998 1998009 4$ Prt MAINT NRC VIO Prt 2A A violation wc:'etentified with two examples of failure to meet 10 CFR 50. Appendix B. Criterion XL Test Control, when Sec: See: 2B c @d beoWMo We WMWuh Tec Item Type (Compliance, Followup,Other), From 02/22/1998 To 08/28/1999
Dole: 11/12/1996 United States Nuclear Regulatory Commission an.:ma,:o3 -
PLANTISSUE MATRIX
- 3 3 sy Dole Legend Type Codes- Temploie Codes Functional Aroos:
BU Bulletin 1A Normat Operations OPS Operations CDR Construction IB Operations During Transients MAINT - Maintenance DEV Deviation 1C Programs and Processes ENG Engineering eel Escolated Enforcementitem 2A Equipment Condition PLTSUP Plant Support IFl inspector follow-up item 28 Programs and Processes OTHER Other LER Ucensee Event Report 3A Work Performance UC Ucensing issue 33 KSA MISC Miscellaneous 3C Work Environment MV Minor Violation 4A Design NCV NonCited Violation 48 Engineering Support NEG Negative 4C Programs and Processes NOED Notice of Enforcement Discretion SA identification NON Notice of Non-Conformance SB Analysis P21 Port 21 SC Resolution POS Positive ID Codes:
SGI Safeguard Event Report NRC NRC STR Strengm Self Self-Revealed URI Unresolved item Ucensee Ucensee VIO Violation WK Weokness Eels are apparent violations of NRC Requirements that are being considered for escolated enforcement action in accordance with the Veneral Statement of Policy and Procedure for NRC Enforcement Action'(Enforcement Policy). NUREG-1600. However, the NRC has not reached its find enforcement decision on the issues identified by the Eels and the PIM entries may be modified when the final decisions are mode.
URis are unresolved items about which more information is required to determine whether the issue in question is on acceptable iterrt a deviation. O nonconformance, or o violation. A URI may also be o potential violation that is not likely to be considered for escolated enforcement action. However, the NRC has not reached its final conclusions on the issues, and the PIM entries may be modified when the final conclusions are mode.
Item Type (Compliance, Followup,Other), From 02/22/1998 To 08/28/1999
,C% United State 3 Nu: lear Regulat:ry Commi cion ee... }
3 PLANT ISSUES MATRIX by SALP Functional Area SEQUOYAH 12-Nov-93 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES T
w y y m m p ;l 9/18/98 Positive IR98-08 NRC Operator response was good for the main feedwater pump problems and the power 1 234 5 excursion caused by a failed open steam dump valve during the Unit 2 startup.
A 00000 s80000 cO 000 9/18/98 Positive IR98-08 NRC The Unit 2 startup was thoroughly briefed and carefully executed by operations 1 234 5 personnel .
A 00000 g00000 cO 000 9/18/98 Positive IR98-08 NRC The licensee conducted a thorough Unit 2 post trip review of the main bank 1 234 5 transformer sudden pressure relay failure.
A 00000 g00000 cO 000 9/18/98 Negative IR98-08 NRC Operators failed to identify an incorrect control _ room tog book entry related to cold 1 234 5 leg accumulator boron concentration. As written, the entry would have required entry into a Technical Specification action statement. A OOOOO s00000 cO 000 9/18/98 Positive IR98-08 NRC Fuel handling personnel were very thorough in the handling and inspection of new 1 234 5 I fuel.
A 00000 B 00000 cO 000 8/4/98 Positive OPS 1R 98-07 NRC The Management Review Committee (MRC) was effectively performing its duties 1 234 5 and plant management was actively involved with the MRC.
A 00000 B 00000 cO 000 FROM: 10/1/97 TO: 11/12/98 Page 1 of 26 FOR PUBLIC RELEASE I.ast Updated: 9/18/98
SEQUOYAH 12-Nov-98 DATE TYPE (s) SEC,SFA l SOURCE (s) ID'd ISSUE (s) SMM CODES 8/4/98 Positive OPS tR 9847 NRC Shift tumovers and rnid-shift briefings continue to be effective in supporting plant 1 234 5 operations .
A 00000 g00000 cO 000 6/26/98 Positive IR 98-06 NRC A positive finding was identified in that the licensee responded promptly and 1 234 5 appropriately to an essential raw cooling water leak inside the Unit 1 annulus which had rendered a radiation monitor containment isolation valve inoperable. A OOOOO B 00000 cO 000 6/26f98 Positive IR 98-06 NRC The inspector concluded that the licensee has irnpiemented compenutory actions 1 234 5 to address the issue of part length control rod drive mechanism potential cracking.
A 00000 s08000 cO 000
&"26/98 Negative IR 98-06 NRC The inspector identified a negative finding when operators failed to locally monitor 1 234 5 the Unit 2 TDAFW pump during a maintenance run of the pump.
A 00000 s00000 cO 000 6/26/98 Negative IR 98-06 NRC A negative finding was identified in that the assistant unit operator's actions of 1234 5 tapping on the valve / valve limit switch, without guidance from the control room, caused loss of the as-found condition of a valve that had failed to futty stroke. A BOOOO B 00000 cO 000 6/26/98 Positive IR 98-06 NRC Operators performed well in addressing the degrading plant conditions prior to the 1234 5 automatic reactor trip and performing the subsequent recovery actions.
A 00000 B B0000 cO 000 5/15/98 Negative IR 9844 NRC The inspectors observed water dripping from the vital 18-B emergency raw cooling 1 234 5 water system 480 voit ac motor control center. This adverse condition had not been identified by the licensee. A OOOOO B 00000 cO 000 FROM: 10/1/97 TO: 11/12/98 Page 2 of 26 FOR PUBLIC RELEASE l ast Updated: 9/18/98
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SEQUOYAH 12-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 3/Y98 Negative IR 98-02 NRC The irwim 5 observed that the AUO written exarninations were a rnarginal tool for 1 234 5 discriminating between a competent and less than competent operator. The inspectors concluded that testing standards for AUOs were very low. A OOOOO B 00000 cO 000 3/5/98 Negative IR 98-02 NRC The insfan 'w = concluded that management attention was needed to ensure that 1 234 5 deficiencies identified during the Main Control Room id= dw uvient drills are promptly and appropriately resched. A OOOOO B 00000 cO 000 3/5/98 Weakness IR 98-02 LICENSEE The evaluation phase of the program (element 4) did not effectively measure the 1234 5 candidtate's level of understanding and mastery of licensed operator knowledges nor did it prepare candidates for the intensity and focus of the NRC license examination. A OOOOO B 00000 cO 000 P]19/98 Weakness IR 97-18 LICENSEE A weakness was identi'ied in operations based on an AUO leaving an area while 1234 5 draining a tank which resulted in a glycol spill, inspecting the wrong sump / pit and signing off a PER as complete, and not removing caution tags after complation of work. Subsequently, the mechanical equipment sump overflowed and resulted in A OOOOO about 1000 gallons of radioactive contaminated /gfycol contaminated water entering B OOOOO the storm drains.
O OOO 2/99/98 NCV IR 97-18 LICENSEE A non-cited violation was identified for the failure to take hourty log readings of AFD 1 234 5 with the AFD monitor alarm inoperable.
A 00000 B 00000 c0 000 2/19/98 Weakness IR 97-18 LICENSEE A weakness was identified because operators failed to promptly identify that a TS 1 234 5 required remote shutdown instrument was inoperable and therefore did not enter the 7-day LCO for approximately 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br />. A OOOOO s00000 cO 000 1/1EG8 NCV 1R 97-17 SELF A NCV was identified for failure to adequately review a hold order clearance which 1 234 5 resulted in an unplanned volume control tank level decrease. An incorrect drain valve was added to the clearance. A BOOOO B 00000 cO 000 FROM: 10/1/97 TO: 11r12/98 Page 4 of 26 FOR PUBLIC RELEASE Last Updated: 9/18/98
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SEQUOYAH 12-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 11/14/97 Weakness IR 97-300 NRC The inspectors identified a weakness in the SRO upgrade candidates knowledge of 1 234 5 rod insertion limit RIL LOW-LOW response. Site-wide training for TS activities regarding the Ril Low-Low alarm was lacki'Y A OOOOO .
s00000 cO 000 11/14/97 Negative IR 97-300 NRC A requalification instructor walked passed baniers and signs warning of a NRC 1 234 5 examination under development.
A 00000 s00000 cO 000 11/14/07 Positive IR 97-300 NRC The training staff was responsive to NRC guidance for developing a more 1 234 5 discriminating examination.
A 00000 '
sD0000 cO 000 11/14f97 Weakness IR 97-300 NRC Poor performance by operator licensing candidates, 5 of 11 failed and SRO upgrade 1 234 5 candidates failed on RO tasks.
A 00000 s00000 cO 000 11/14/97 Negative IR 97-300 NRC During simulator operations, operators had diffculty controlling AFW flow while 1 234 5 performing EOP steps. There was a lack of detailed procedura! guidance for taking control of the the AFW control valves to prevent overfilling the SGs. A OOOOO s00000 cO 000 11/14f97 Weakness IR 97-300 NRC Poor Quality of Operator Licensing audit and remediation programs. The RO 1 234 5 candidate was allowed to retake the examination without formal remediation.
A 00000 sO0000 cO 000 10/10/97 Weakness IR 97-12 NRC One weakness was identified regarding a lack of discrimination in the in-plant Job 1 234 5 Performance Measures used as exarnination tools. Four of the six In-plant JPMs were considered too simplistic to provide meaningful feedback to the Requalification A OOOOO s000OO cO 000 FROM310/1/97 TO: 11/12/98 Page 6 of 26 FOR PUBLIC RELEASE Last Updated: 9/18/98 1
v SEQUOYAH 12-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 10/10/97 Positive IR 97-12 NRC The requalification program was effective in maintaining licensed operator 1234 5 pmficiency and knowledge. The requalification examination was adequately discriminating and comprehensive.
A OOOOO e00000 cO 000 10/10/97 Negative IR 97-12 LICENSEE Assistant unit operators did not property position the stator coohng water pump 1 234 5 discharge valve which resulted in a rnomentary loss of stator cooling. Operators failed to property lock a valve in position and the valve subsequently went closed. A OOOOO sD0000 cO 000 10/10/97 Negative IR 97-12 NRC Operations did not appropriately apply TSs with regard to residual heat removat 1 234 5 system operability. The CCS supply valve for the RHR heat exchanger was tagged out for maintenance; however, the licensee did not enter the action statement for the RHR system being inoperable. The licensee did not exceed the LCO.
A OOOOO OOOOO cO 000 10/10/97 NCV IR 97-12 LICENSEE A non-cited violation was identified for failure to follow procedures during an 1 234 5 essential raw cooling water valve realignment Operators signed off popm weik for common unit vs. Unit 1, which they were working on.
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9/18/98 Weakness IR98-08 LICENSEE Deficiencies were observed in ice condenser housekeeping. Practices used to free 1 234 5 frozen ice baskets have resulted in minor ice basket damage in Unit 2. Frosting of the outer ice passages was prevalent.
A OOOOO s00000 cO 000 9/18/98 Weakness ENG IR98-08 LICENSEE Deficiencies were identified in vendor technical guidance and weaknesses were 1 234 5 identified in the licensee's maintenance and inspection program for type DS 532 480 Vac circuit breakers .
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B 00000 l cO 000 9/18/98 Positive IR98-08 NRC The licensee has successft.ly implemented the initial phase of a design change
- \ 1 234 5 notice to replace the existing emergency diesel generator batteries.
A 00000 s00000 cO 000 FROM: 10/1/97 TO: 11/12/98 Page 7 of 26 Last Updated: 9/18/98 FOR PUBLIC RELEASE
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SEQUOYAH 12Mw-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 9/18/98 Positive (R98-08 LICENSEE The replacement of suspect coupling capacitor voltage transformers wrs a good 1234 5 example of the licensee's effort to improve the reliability of the switchyard.
A 00000 s00000 cO 000 9/18/98 Positive tR98-08 NRC The licensee's replacement and calibration of the pressurizer level transmitter for 1 234 5 instrument 2-LT 68-320 was well performed using detailed maintenance and calibration procedures. A OOOOO e00000 cO 000 9/18/98 Positive IR98-08 NRC The licensee imrslemented a well-planned forced outage schedule following the Unit 1 234 5 2 trip on August 27.
A 00000 B 00000 c0 000 8/4/98 Negative PLT SUP IR 98-07 LICENSEE A craftsman did not adequata understanding the effects of installing test 1 234 5 equipment on operating piare equipment when measuring the output frequency of the uninterruptable power supply (UPS), consequently the UPS power supply breaker trip and resulted in the partialloss of the site security system.
A OOOOO c OOOOO cO 000 8/4/98 Positive SAQV IR 98-07 LICENSEE The periodic assessment report demonstrated that the licensee had evaluated 1 234 5 performance, condition monitoring. associated goals and preventive maintenance l activities for systems, structures and components within the w: ope of the Maintenance Rule.
A OOOOO OOOOO cO 000 8/4/98 Positive ENG IR 98-07 LICENSEE A thorough evaluation into the root cause of the Unit 2 turbine driven auxiliary 1 234 5 feedwater pump packing failure.
A 00000 e00000 cO 000 8/4/98 Negative PLT SUP IR 98-07 NRC A poor work practice was observed when a craftsman used the plant telephone 1 234 5 while wearing protective yellow gloves.
A 00000 e00000 cO 000 FROM: 10/1/97 TO: 11/12/98 Page 8 of 26 FOR PUBLIC RELEASE Last Updated: 9/18/98
SEQUOYAH 12-Nov-98 1
DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 6/26/98 Strength tR 98-06 NRC A strength was identified in that eddy current data evaluation and rnanagement tools 1 234 5 were strong components of the licensee's program for steam generator degradation management. A OOOOO sD0000 c0 000 6G6/98 Negative IR 98-06 NRC A concem was identified for the potential improper compression setting and the 1234 5 potentialinadequate post maintenance testing of the shutdown bus attemate supply breaker. A OOOOO s00000 cO 000 6G6/98 Weakness IR 9846 NRC A weakness was identified for a less than effect!ve program for the identification and 1 234 5 correction of water intrusion into electrical components.
A 00000 B 00000 cO 000 6G6/98 Weakness IR 98-06 NRC A concem was identified with the potential deficiencies in maintenance and 1 234 5 inspection procedures which resulted in ice condenser ice basket damage.
A 00000 s00000 cO 000 6/26/98 Weakness IR 98-06 NRC A weakness was identfied in the Work Order process relating to documentation 1 234 5 deficiencies.
A 00000 s00000 cO 000 EG6/98 Positive IR 98-06 NRC A positive finding was identified in that post maintenance testing was conducted 1 234 5 appropriately and in a manner consistent with procedural and regulatory requirements. A OOOOO eD0000 cO 000 6/26/98 Negative IR 98-06 NRC A negative finding was identfied for the licensee's failure to establish a preventative 1 234 5 maintenance activity (18 years) for sampling or changing emergency diesel generator bearing oil. A OOOOO B 00000 cO 000 FROM: 10/1/97 TO: 11/12/98 Page 9 of 26 FOR PUBLIC RELEASE Last Updated: 9/18/98
SEQUOYAH 13-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 6f26/98 Positive IR 98-06 NRC A positive finding was identified in that the licensee executed a well planned forced 1 234 5 outage schedule following the May 19,1998. Unit 1 reactor trip.
A 00000 B 00000 cO 000 6/12/98 Weakness IR 98-05 NRC The team found that the licensee's root cause determinations and corrective actions 1 234 5 met the requirements of Criterion XVI. The inspectors considered the analysis conscientious, self critical and a good example of a thorough root cause analysis. A OOOOO sD0000 cO 000 f312/98 Positive IR 98-05 NRC The inspectors found that procedure for commercial grade dedication provided 1 234 5 adequate guidance for the procurement and dedication of commercial grade material with minor exceptions. A OOOOO s00000 cO 000 6/12/98 Weakness IR 98-05 NRC The vendor interface program was in concert with the NRC position. The team 1 234 5 identified a lack of a vendor manual for the Type DB-25 circuit breakers.
A 00000 s00000 cO 000 6/12/98 Strength IR 98-05 NRC The team concluded that the resolution of issues expressed in operating documents, 1 234 5 Part 21 reports was good. A strength observed was the tendency to expand the scope review for the documents beyond the minimum acceptable. A OOOOO a00000 cO 000 6/12/98 Positive IR 98-05 NRC The team found the licensee was complying with 10 Cm 50.65 Maintenance Rule 1 234 5 with regard to treatment of power circuit breakers.
A 00000 a00000 cO 000 6/12/98 Weakness IR 98-05 NRC The team performed a detailed review of failures of medium-voltage circuit 1 234 5 breakers. A sample of failures on 480-Vac circuit breakers was reviewed.
A 00000 e00000 cO 000 FROM: 10/1/97 TO: 11/12/98 Page 10 of 26 FOR PUBUC RELEASE Last Updated: 9/18/98
SEQUOYAH 12-Nov-98 i
DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 6/12/98 Positive MAINT IR 98-05 NRC The team's review of maintenance records for ten safety-related circuit breakers 1 234 5 indicated that the program had been implemented, except that one record could not be located. Licensee's self assessment found as many as 36 breakers had overdue A OOOOO B 00000 cO 000 6/12/98 Strength IR 98-05 NRC The preventive maintenance procedures for the 6.9 kV and 480Vac breakers were of 1 234 5 a type appropriate to the circumstances. The maintenance procedures were i A OOOOO considered a strength.
B 00000 cO 000 6/12/98 Positive tR 98-05 NRC The team concluded that the circuit breakers were performing well, but that 1 234 5 refurbishment was needed based on the age of the breakers and lack of any previous refurbishment during the 20 years of service. The licensee had recently initiated a refurbishment program A OOOOO OOOOO cO 000 6/12/98 Positive IR 98-05 NRC The switchgear and surrounding areas were found in good material condition in a 1 234 5 walkdown inspection with no deficiencies identified.
A 00000 s00000 cO 000 5/15/98 MISC IR 98-04 NRC A concem was identified with the process for randomly sampling of the ice 1 234 5 condenser ice basket weights due to approximately one third of the ice baskets in the Unit 1 and a lesser percentage of baskets in the Unit 2 ice condenser, being frozen in place.
A OOOOO OOOOO cO 000 5/15/98 Positive IR 98-04 NRC Based on a randorn visual check of the Unit 1 ice condenser, it appeared that the 1 234 5 ticensee's program had been aggressive and effective in maintianing passages in a free flow condition, minimizing debris in the ice condenser, and minimizing ice buildup on the intermediate doors.
A OOOOO OOOOO c0 000 4/6/98 Positive IR 98-03 NRC The corrective action program was generally implemented in m,w.&@ with the 1 234 5 requirements of procedure SSP-3.4, Corrective Action, Rev. 23. The program followed the guidance of GL 91-18, Rev.1, for disposition of degraded and non-conforming conditions and fully satisfied the requirements of 10 CFR 50 Appendix B A OOOOO
, Criterion XVI. B OOOOO cO 000 FROM: 10/1/97 TO: 11/12/98 Page 11 of 26 FOR PUBLIC RELEASE Last Updated: 9/1ti/98
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SEQUOYAH 12-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 1/16/98 Positive IR 97-17 NRC Improvements were noted in the performance of Rad Monitoring system and 1 234 5 housekeeping and material condition were considered to be good. The process for evaluation of safety impact prior to removal of equipment from service was adequare.
A OOOOO sOOOOO cO 000 9/1E198 Positive IR 97-17 NRC The licensee's actions to address the failure of 2-FCV-6-166A were appropriate and 1 234 5 consistent with 10 CFR 50.65. 2-FCV-6-166A is the level control valve from feetwater heater 2C4 to feedwater heater 2CS, which broke in half due to water hammer conditions in the line.
A OOOOO OOOOO cO 000 1/16/98 Positive IR 97-17 NRC 'the licensee had implemented the containment inspection rule in a satisfactory 1 234 5 manner.
A 00000 s00000 cO 000 1/16/98 Weakness IR 97-17 NRC A weakness was identified with the NDE program, the licensee was unable to 1 234 5 produce records supporting the NDE procedure qualification, did not adequately review visual acuity certifications and had unclear linkage for traceability for UT calibration standards.
A OOOOO OOOOO cO 000 1/16/98 NCV IR 97-17 SELF A NCV was identified for failure to meet procedural requirements for work control 1 234 5 and clearance control that led to an auxiliary building isolation (ABi) actuation signal and temporary lose of a significant number of plant rad monitors and recorders. 20 morutors and 10 recorders were lost.
A OOOOO OOOOO cO 900 1/16/98 Weakness IR 97-17 LICENSEE A weakness was identified for not having a preventive maintenance program in place 1 234 5 to periodically refurbish ASME Class 2 and 3 Section XI relief valves which msulted in undetected setpoint drift problems. A OOOOO s00000 cO 000 1/16/98 Negative IR 97-17 SELF A weakness in the pressurizer master pressure controller calibration procedure was 1 234 5 noted for not ensuring proper operation of the setpoint dial.
A 00000 s00000 c0 000 FROM: 10/1/97 TO: 11/12/98 Page 13 of 26 FOR PUBLIC RELEASE Last Updated: 9/18/98
SEQUOYAH 12-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 12/12/97 Positive IR 97-16 LER 97-S01 NRC The inspector concluded that the licensee's investigation and the response to the 1234 5 Unit 2 damaged conductors vandalism event was excellent. The Heensee reported the event to the NRC in accordance with regulations. A OOOOO B 00000 cO 000 12/12/97 Negative IR 97-16. LER 97-S01 LICENSEE On October 17,1997, the licensee identified that 11 individual conductors for a 1 234 5 containment penetration had been severty damaged due to vandalim by an unknown individual Considered to be a random act by an unknown individual. A OOOOO s00000 cO 000 12/8/97 Weakness IR 97-14 SELF A weakness was identified for the lack of planning and coordination of surveitlance 1234 5 activities that resulted in the generation of an unexpected reactor trip signal and tnpping of the reactor trip breakers, while in Mode 5. A OOOOO B 00000 cO 000 12/8/97 Positive IR 97-14 NRC Changes in maintenance oversight, planning and work practices resulted in 1 234 5 improved maintenance performance during the Unit 2 refueling outage.
A 00000 s00000 cO 900 12/B!97 MISC ENG IR 97-14 SELF The licensee addressed issues related to the "D* station air compressor high oit 1 234 5 temperature trip setpoint, unexpected auto closure of the air compressor ERCW cooling valve, and drifting of the service air isolation valve press setpoint. A OOOOO sD0000 cO 000 12/8/97 Positive IR 97-14 NRC The licensee has made significant improvements to the freeze protection program, 1 234 5 most notably at the ERCW pumping station.
A 00000 B 00000 cO 000 12/8/97 Negative IR 97-14 SELF A weakness was identified for not using test leads of sufficient length, resulting in a 1 234 5 blown fuse on one of the three loss of voltage sensors on the 2A-A 6.9 kv shutdown boards and entry into a TS action statement. A OOOOO s00000 cO 000 FROM: 10/1/97 TO: 11/12/98 Page 14 of 26 FOR PUBLIC RELEASE Last Updated: 9/18/98
SEQUOYAH 13-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 11/21/97 LER LER 97-013-00 LICENSEE On October 22,1907, the licensee identified that the breaker for the fuel handling 1 234 5 exhaust fan *A* did not meet its TS surveillance requirement (SR 4.8.3.3.) The surveillance procedu's had been inadequately revised in 1990. The procedure was subsequently revised and the breaker was tested successfully.
A OOOOO OOOOO cO 000 10/10/97 Positive SAQV IR 97-12 NRC The licensee conducted a thorough review of root and contributing causes. and 1 234 5 corrective actions, for the control air system initiated transients on August 1,1997.
A 00000 s00000 cO 000 10/10/97 Positive IR 97-12 NRC Replacement of the control air compressors contributed to improved material 1234 5 condition of the plant.
A 00000 s00000 cO 000 10/10/97 Negative SAQV IR 97-12 NRC The licensee did not effectively review the impact of the longs *.anding poor material 1 234 5 condition of the cor. trol air system on activities such as clearance boundaries, which contributed to the dual unit run back and Unit 1 reactor trip on August 1,1997, A OOOOO B 00000 cO 000 snW+&5%
9/18/98 Positive 98-08 NRC Modificctions to the Spent Fuel Pool cooling system were successfuity implemented 1 234 5 due in part to the thorough evaluation of the design change notice by engineering and site management . A OOOOO s00000 cO 000 8/4/98 VIO IR 98-07 NRC A violation wMi two examples was identified for failure to meet the calibration 1 234 5 requiements of TS 4.3.1.1 for the pressurizer level transmitters.
A 00000 sD0000 cQ 000 8/4/98 Negative IR 98-07 NRC The licensee's Records Retention Program could not provide documentation to 1 234 5 sepport the 1988 changes to the pressurizer level instrument calibration procedures and to the repairs made to the pressurizer level sensing line nozzles. A OOOOO B 00000 c0 000 FROM: 10/1/97 TO: 11/12/98 Page 15 of 26 FOR PUBLIC RELEASE Last Updated: 9/18/98
SEQUOYAH 12-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 8/4/98 VIO SAOV 1R 98-07 NRC A violation with three examples was identified for failure to initiate a Problem 1234 5 Evaluation Report (PER) to identify and promptly correct the deficient conditions exhibited by pressurizer level instrument 2-LT-68-320- A OOOOO B 00000 c0 000 6/26/98 VIO IR 9846 NRC One violation (three examples) for failure to adequately implement Section XI code 1 234 5 testing requirements.
A 00000 B 00000 cO 000 6/26/98 Positive IR 98-06 NRC The acquisitim of a new software program for analysis, tracking and trending IST 1 234 5 data was considered a positive addition to the IST program.
A 00000 g00000 cO 000 6/26/98 Positive IR 98-06 NRC Observation of pump tests , review of pump test procedures, and review of pump 1234 5 parameter trend data indicated the licensee has established and implemented an adequate pump IST program. A OOOOO s00000 cO 000 6/26/98 Positive IR 98-06 NRC A positive finding was identified based on enginering support of facilities and 1 234 5 equipment when a licensee identified steam generator hydraulic snubber leak was property assessed for operability and a thorough corrective action plan was promptly implemented.
A OOOOO OOOOO cO 000 6/26/98 Weakness IR 98 -06 NRC A weakness was identified due to continuing steam dump system problems which 1 234 5 resulted in the May 19,1998 water hammer event and piping support damage.
A 00000 s00000 cO 000 E126/98 Positive IR 98-06 NRC A positive finding was identified based on system Engineering successfully 1 234 5 developing and implementing an action plan to remove boron from the Unit 1 lower compartment coolers. A OOOOO B 00000 cO 000 FROM: 10/1/97 TO: 11/12/98 Page 16 of 26 FOR PUBLIC RELEASE 1.ast Updated: 9/18/98
SEQUOYAH 12-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 6/26/98 DEV IR 98-06 NRC A violation was identified for failure to perform an adequate safety evaluation prior to 1 234 5 making modifications to the waste gas analyzer system.
A 00000 s00000 cO 000 S/1Ef98 Positive IR 98-04 NRC The licensee has taken appropricte corrective actions to periodically monitor and 1 234 5 refurbish reactor protection system power supplies.
A 00000 B 00000 cO 000 4/6/98 MISC PLT SUP IR 98-03 NRC The inspectors noted several potential problems during the review of the high 1 234 5 oxygen concentration in the Unit 1 PRT. Further review will be necessary for the following items: potential failure to meet the UFSAR requirements for having an automatic gas analyzer, not adequately revising the UFSAR. inappropriately closing A OOOOO the design change pacakage, and not establishing a periodic oxygen / hydrogen B OOOOO sampling pmgran cO OOO 3Of98 MISC IR 98-01 NRC A concem was identified related to an unverified FSAR chapter 15 Accident Analysis 1 234 5 assumption for 10 minute operator action on a main feedwater piping rupture.
A 00000 eG0000 cO 000 3 0 /98 Weakness SAOV IR 98-01 NRC A weakness was identified for engineering's poor independent review of calculations 1 234 5 and technica! evaluations which failed to identify errors.
A 00000 B 00000 cO 000 3r30/98 Strength SAOV IR 98-01 NRC A strength was identified for engineering root cause determination and resolution of 1 234 5 an industry wide problem related to degraded centrifugal pump bearings (black oil).
A 00000 B 00000 c0 000 3fD/98 VIO IR 98-01 NRC A 50.59 violation was identified for failure to perform a 50.59 screening on changes 1 234 5 made to 2A-A MDAFW pump during maintenance which replaced the rotating element. A OOOOO B 00000 cO 000 FROM: 10/1/97 TO: 11/12/98 Page 17 of 26 FOR PUBLIC RELEASE Last Updated: 9/18/98
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SEQUOYAH 12-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 1/16/98 Positive SAQV IR 97-17 NRC The management review committee demonstrated good safety sensitivity toward 1 234 5 conditions adverse to quality and assured that the scope of review and apparent causes were extens;ve.
A OOOOO a00000 cO 000 1/16/98 Positive IR 97-17 SELF The licensee promptly identified and foDowed up the Unit 2 fuel misload event and 1 234 5 ensored the cause was identified and corrected. The fuel manufacturer had rovided improper loading instructions to the site which led to inispositioning 16 fuel assemblies.
A OOOOO OOO cO 000 12/8/97 Positive IR 97-14 NRC Mcdifications implemented during the refueling outage appeared to be 1 234 5 correcting / addressing many long-standing plant deficiencies.
A 00000 g00000 cO 000 11/2/97 Weakness SAOV NRR Letter to TVA NRC License amendment requests for SON and BFN to remove QA requirements were 1 234 5 submitted prior to submittal of NOA Plan change. TVA did not provide a clear reference to requirements to the NOAP and often did not provide any justification for the changes. The result was a lengthy request for additional information and delay A OOOOO in review of the amendments and revision 7 to NOAP. B OOOOO cO 000 10/10f97 Positive PLT SUP IR 97-12 NRC The licensee's upgrade of the ERCW chlorination system should improve the overall 1 234 5 efficiency of the system and reduce down time due to piping leaks. The system has had a history of piping failures and excessive down time. A OOOOO B 00000 cO 000 10/10/97 Negative IR 97-12 SELF The relief va've setpoints for the safety injection system drifted high and appears to 1 234 5 be a recurring problem. The licensee is in the process of determining the cause of the relief valve setpoint drift. A OOOOO g00008 CO 000 10/10/97 Negatrve IR 97-12 SELF Back leakage from the reactor coolant system, due to leaking check valves, caused 1 234 5 a pressure transient in the Safety injection system. Leakage was within the allowable limits and the system was analyzed for the higher pressure. The check valves were known to leak.
A OOOOO OOO cO 000 j afq FROM: 10/1/97 TO: 11/12/98 Page 19 of 26 FOR PUBLIC RELEASE Last Updated: 9/18/98
SEQUOYAH 12-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 9/18/98 Positive IR98-08 NRC On August 12,1998, the licensee conducted an effective Radiological Emergency 1 234 5 Plan drill.
A 00000 B 00000 c8 000 8/4/98 Positive IR 98-07 NRC The total dose from the 40 CFR 190 calculation for the radiological impact from 1 234 5 facility operation was < 1% of the regulatory limit.
A 00000 g00000 cO 000 8/4/98 Positive IR 98-07 NRC The primary water chernistry control program and secondary water quality were 1 234 5 being implemented in a-ve,c6 with TS requiements.
A 00000 B 00000 cO 000 8/4/98 Positive IR 98-07 NRC The licensee had effectively implemented the program for shipping and receiving 1 234 5 radioactive materials to meet NRC and Department of Transportation regulations.
A 00000 B 00000 cO 000 8/4/98 Positive IR 98-07 NRC Radiation work activities were well planned and worker radiation dose were 1 234 5 maintained well below regulatory limits.
A 00000 B 00000 cO 000 8/4/99 Positive SAQV IR 98-07 NRC Nuclear Assurance assessment of the fire protection program was comprehensive . 1 234 5 and effective in identifing program performance to management . Previously identified findings corrective actions were good and implemented in a timely A OOOOO sOOOOO c0 000 8/4/98 Positive MAINT IR 98-07 NRC The maintenance ano miliance program for the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> emergency lighting 1 234 5 system demonstrated ercergency lighting was operable and correctly aimed to illuminate post-fire alternate shutdown equipment. A OOOOO s00000 c8 000 FROM: 10/1/97 TO: 11/12/98 Page 20 of 26 FOR PUBLIC RELEASE I.ast Updated: 9/18/98
SEQUOYAH 12-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 8/4/98 Posibve IR-98-07 NRC The ob%rved level of plant housekeeping reflected good organization and 1 234 5 cleanliness practices of plant personnel and performance.
A 00000 B 00000 cO 000 8/4/98 Positive ENG IR 98-07 NRC The RCP oil collection system design, procedural guidance and operator action 1 234 5 when RCP oil feak occurred met licensee commitments identified in the UFSAR for wn v6ce with 10 CFR 50, Appendix R. Section 111.0. A OOOOO B 00000 cO 000 8/4/98 Positive ENG IR 98-07 NRC Fire barrier seal designs were well supported by test documentation, vendor data. 1 234 5 design data, and inspection records. For deviation from fire barrier configurations engineering evaluations qualified by tests satisfied the guidance of NRC GL 86-10. A OOOOO B 00000 cO 000 8/4/98 Positive IR 98-07 NRC The use and storage of combustibles in safety related areas and the rnaterial 1 234 5 condition in the plant indicated that plant departments were property implementing their responsibilities for control of combustible materials. A OOOOO B 00000 cO 900 6/26/98 Positive IR 98-06 NRC A positive finding was identified in that the security force members adequately 1234 5 demonstrated that they have the requisite knowledge necessary to effectively implement the duties and responsibilities associated with their day-to-day duties. A OOOOO B 00000 c8 000 6/26/98 Positive IR 98-06 NRC The exceitent Engineering and instrumentation and controls support was the major 1 234 5 contributing factor to continued operability of the detection and assessment equipment. A OOOOO B 00000 cO 800 6/26/98 Positive IR 98-06 NRC A positive finding was identified in that the licensee's security facilities and 1 234 5 equipment were determined to be very well maintained.
A 00000 s00000 c0 000 FROM: 10/1/97 TO: 11/12/98 Page 21 of 26 FOR PUBLIC RELEASE Last Updated: 9/18/98
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SEQUOYAH 12-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 45/98 Positive SAOV IR 98-03 NRC The inspectors determined the Ecensee was effectively conducting formal radiation 1 234 5 protection audits as required by TS and conducting self-assessments The Econsee was effectively developing corrective action plans and completing corrective actions in a timely manner.
AOOOOO sOOOOO cO 000 4/6/98 Positive IR 98-03 NRC The meteorological instrumentation had been adequately maintained and the 1 234 5 meteorological monitoring program had been effectively implemented.
A 00000 B 00000 cO 000 4/6/98 Positive IR 98-03 NRC The water chemistry control program for iru iRudig primary and secondary water 1 234 5 quality had been implemented, for those parameters reviewed, in accordance with the TS requirements. A OOOOO B 00000 cO 000 4/6/98 Positive IR 98-03 NRC The Ecensee had effectively implemented a program for shipping and receiving 1234 5 radioactive materiais as required by NRC and DOT regulations.
A 00000 B 00000 cB 000 4/6/98 Positive IR 9843 NRC Contamination control was effective. 1 234 5 A 00000 B 00000 c3 000 40198 Positive IR 98-03 NRC Radiation work activities were planned, radiation worker doses were being 1 234 5 maintained well below regulatory limits and the Ecensee was continuing to maintain exposures ALARA. A OOOOO B 00000 c3 000 4/6/98 Positive IR 98-03 NRC Radiological faciFdf conditions and housekeeping it' radioactive waste storage areas. 1 234 5 he&hh physics facilities, auxiliary building and refueling floor were observed to be good and material was labeled appropriately. A OOOOO B 00000 cO 000 FROM: 10/1/97 TO: 11/12/98 Page 23 of 26 FOR PUBLIC RELEASE Last Updated: 9/18/98
SEQUOYAH 12-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 4/6/98 VIO IR 98-03 NRC A violation was identified for failure to initiate a problem evaluation report after 1234 5 chernistry analysis of the Unit 1 PRT sample indicated a high oxygen concentration.
A second example of this violation was identified for the failure to initiate a work request when chemistry personnel could not obtain a PRT sample due to apparent A OOOOO dockage of the sample line. B OOOOO cO 000 TJ19/98 Weakness MAINT IR 97-18 NRC A weakness was identified based on plant support laborers cleaning the abandoned 1 234 5 upper head injection pit instead of the AEB sump and the assigned rad con.
technician controlling the RWP activities in the abandoned pit vs. the AEB sump. A OOOOO s00000 cO 000 PJ19/98 Weakness OPS IR 97-18 NRC A weakness was identified in that appropriate levels of management were not 1234 5 informed that posted frisking requirements had not been met and later that day additior.al personnel failed to meet the same posted frisking requireraents. A OOOOO sD0000 cO 000 2/10/98 VIO OPS IR 97-18 NRC A violation with two examples was identified for rot frisking out of a posted 1 234 5 radiologically controlied area.
A 00000 s00000 cO 000 12/8/97 MISC IR 97-14 SELF When airbome radiation was detected in the control room, the airbome levels were 1 234 5 well below established limits and the control room ventilation system functioned as designed. 4 OODD0 s00000 cO 000 12/0/97 Positive IR 97-14 LICENSEE During the U2C8 outage, the total estimated TLD exposure was 140 REM, which 1 234 5 was the site's best ALARA performance for an outage by more than 70 REM.
A 00000 s00000 cO 000 12/8/97 Strength IR 97-14 NRC The fire protection program implementation was effective. Good performance noted 1 234 5 in testing, reduction of inoperable components, transient combustible control, fire brigade organization, oversight of program, and comprehensive audits. A OOOOO s00000 cO 000 FROM: 10/1/97 TO: 11/12/98 Page 24 of 26 FOR PUBLIC RELEASE Last Updated: 9/18/98 k_ _ _
SEQUOYAH 12-Nov-93 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd . ISSUE (s) SMM CODES ILG/97 Weakness IR 97-15 NRC A weakness was identified for the delay in declaring a NOUE during the October 5, 1 234 5 1996, transformer explosion.
A 00000 B 00000 cO 000 11/3/97 Negative IR 97-15 NRC The effectiveness of the OSC regulatory audit had decreased, the testing of 1234 5 emergency response equipment had a limited focus, two sirens had a lengthy history of consecutive failures withott. corrective maintenance, errors were identified with an EP procedure , an EP pro;edure did not dearty establish training requirements, A OOOOO and the emergency resporre organization exams were not challenging. B DOOOO cO 000 11/3/97 Positive IR 97-15 NRC The emergency facilities and equipment were satisfactonly maire.ained, the public 1234 5 notification siren was satisfactority tested, the emergency action levels were well organized, EP continued to receive management support, the EP audit was organized and objective, and the licensee was adequately tracking and resolving drill A OOOOO comments. B OOOOO cO 000 FROM: 10/1/97 TO: 11/12/98 Page 25 of 26 FOR PUBLIC RELEASE Last Updated: 9/18/98
SEQUOYAH 12-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES SMMTemplate Codes: SALP Functional Areas: ID Code:
1A , OPERATION PERFORMANCE - Normal Operations l [ LICENSEE l LICENSEE 1B jOPERATION PERFORMANCE - Operations During Transients ENG l ENGINEERING
- jNPO ;NRC 1C ; OPERATION PERFORMANCE - Programs and Processes MAINT l MAINTENANCE ;SELF-REVEALED lSELF 2A l MATERIAL CONDITION - Equipment Condition OPS ' OPERATIONS I 2B l MATERIAL CONDITION - Programs and Processes PLT SU 'jPLANT SUPPORT 3A , HUMAN PERFORMANCE Work Performance SAQV ! SAFETY ASSESSMENT & QV 38 l HUMAN PERFORMANCE - KSA 3C ; HUMAN PERFORMANCE-Work Environment 4A
- ENGINEERING / DESIGN - Design 48 { ENGINEERING / DESIGN - Engineering Support 4C , ENGINEERING / DESIGN- Programs and Processes SA : PROBLEM IDENTIFICATION & SOLUTION - Identifcation 58 l PROBLEM IDENTIFICATION & SOLUTION - Analysis SC .PROPLEM IDENTIFICATION & COLUTION - Resolution Eels are apparent violations of NRC requirements that are being considered for escalated enforcement action in accordance with the
- General Statement of Policy and Procedure for NRC Enforcement Action" (Enforcement Policy), NUREG-1600. However, the NRC has not reached its final enforcement decision on the issues identified by the Eels and the PIM entries may be modified when the final decisions are made. Before the NRC makes its enforcement decision, the licensee will be provided with an opportunity to either (1) respond to the apparent violation or (2) request a predecisional enforcement conference.
URis are unresolved items about which more information is required to determi9e whether the issue in question is an acceptable item, a deviation, a nonconformance, or a violation.
However, the NRC has not reached its final conclusions on the issues, and the PIM entries may be modified when the final conclusions are made.
FROM: 10/1/97 TO: 11/12/98 Page 26 of 26 Last Updated. 9/18/98 FOR PUBLIC RELEASE t
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