ML20204J545

Advises of NRC Planned Insp Effort Resulting from Sequoyah Plant Performance Review on Feb 1998-Jan 1999.Historical Listing of Plant Issues & Details of NRC Insp Plan for Next 8 Months Encl

ML20204J545
Person / Time
Site:	Sequoyah
Issue date:	03/19/1999
From:	Fredrickson P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Scalice J TENNESSEE VALLEY AUTHORITY
References
NUDOCS 9903300117
Download: ML20204J545 (32)

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L March 19, 1999 j

Tennessee Valley Authority ATTN: Mr, J. A. Scalice Chief Nuclear Officer and Executive Vice President 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 i

SUBJECT:

PLANT PERFORMANCE REVIEW- SEQUOYAH NUCLEAR PLANT

Dear Mr Scalice:

On February 8,1999, the NRC staff completed a Plant Performance Review (PPR) of the Sequoyah Nucisar Plant. The staff conducts these reviews for all operating nuclear power plants to develop an integrated understanding of safety performance. The results are used by NRC management to facilitate planning and allocation ofinspection resources. PPRs provide NRC management with a current summary of licensee performance and serve as inputs to the NRC's senior management meeting (SMM) reviews. PPRs examine information since the last assessment of licensee performance to evaluate long term trends, but emphasize the last six months to ensure that the assessments reflect current performance. The PPR for Sequoyah - 1 involved the participation of all technical divisions in evaluating inspection results and safety performance information for the period of February 1998 through January 1999. The NRC's most recent summary of licensee performance was provided in a letter of April 1,1998, and was

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discussed in a public meeting with you on April 21,1998. i As discussed in the NRC's Administrative Letter 98-07 of Octnber 2,1998, the PPR provides an assessment of licensee performance during an interim period that the NRC has suspended its Systematic Assessment of Licensee Performance (SALP) program. The NRC suspended its SALP program to complete a review of its processes for assessing performance at nuclear power plants. At the end of the review period, the NRC will decide whether to resume the SALP

, program or terminate it in favor of an improved process. In addition, the Sequoyah facility was selected to be a pilot plant for the new reactor oversight process. We will notify you of any associated chariges to planned inspections by separate correspondence in the near future.

During the last six months, Unit 1 operated at 100 percent power until a shutdown on September 9, for a refueling outage. The unit was restarted on October 8 and operated at full power until November 9 when an automatic trip occurred due to a loss of a vital inverter. The unit returned to 100 percent power on November 11. On November 20, power was reduced to 35 percent to enter containment and shut a leaking vent valve on a reactor coolant system loop flow instrument. Unit 1 operated at full power for the remainder of this period.

Unit 2 operated at 100 percent power until August 27,1998, when the unit automatically tripped due to a failed main bank transformer sudden pressure relay. The unit resumed full power on August 30. On October 15, the main bank transformer sudden pressure relay failed again 9903300117 990319 PDR G ADOCK 05000327 PDR

. . . . - .~..- - - - -- - . _ . - . - - - - . - - . - - . - - ,

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TVA 2 resulting in an automatic reactor trip. Unit 2 resumed full power on October 17 and has

remained there for the remaindsr of the period.

Ov'erall, perfonnance at Sequoyah was acceptable. Both units operated at high capacity factors and Unit 2 completed a successful refueling outage. Audits and self-assessments continued to ,

provide positive results in plant performance. Some performance challenges during the period were in the areas of licensed operator training and operator performance; electrical breaker corrective and preventive maintenance; and the identification, evaluation and resolution of i adverse conditions in several activities.

i Performance in Operations was consistent. Management involvement in Operations continued )

to be effective in resolving emergent issues. Licensed operator performance during routine  ;

operations and response to several reactor trips was generally effective. Weakness in licensed operator training was indicated by the operator's failure to implement and follow emerger.cy operating procedures following a November 9,1998 reactor trip, and several failures to enter or use the correct technical specification. Training program weaknesses were also identified in the areas of license examination development and reactor operator candidate evaluation.

Procedure weaknesses continued to be identified, as were deficiencies in the performance of assistant unit operators (AUO) concerning attention to detail when performing AUO rounds.

Performance during the period does not warrant any additional inspection effort above the core inspection program. Some increased emphasis will be placed on core inspections of the licensed operator training program and its implementation.

Maintenance performance was consistent in that maintenance and outage activities continued to be effectively implemented and predictive and preventive maintenance activities were performed i in accordance with requirements. Insufficient incorporation of vendor technical manual guidance  !

led to breaker failures following refurbishment. Significant improvements were subsequently j made in the breaker test and maintenance programs. Some material condition deficiencies I were identified in the ice condensers, but overall material condition of the plant continued to improve. Self-r.csessment activities remained at a high level of participation, with alllevels of the maintenance staff contributing to the identification of deficiencies. In addition to the core Inspection program, two regionalinitiative inspections are planned. One of the inspections will place emphasis on breaker program ma!ntenance and post maintenance testing following refurbishment. The other regional initiative will focus on ice condenser material condition.

Performance in Engineering was consistent, with performance remaining e'fective in program implementation, engineering processes, problem analysis, and evaluations. However, some examples of inadequate design control process implementation were identified as noted by the

. failures to meet calibration requirements for pressurizer level instruments, to perform an adequate safety evaluation prior to making modifications to the waste gas analyzer system, and also by not adequately correcting design problems with the steam dump system. Although performance in engineering support was effective overall, there were some problems with implementing the problem identification process as shown in examples for failure to initiate a problem evaluation report to correct pressurizer level deficiencies and to adequately implement inservice testing of valves in accordance ASME,Section XI test requirements. Performance during the period does not warrant any additional inspection effort above the core inspection

TVA 3 1

program. Some increased emphasis will be placed on core inspections of design engineering and engineering support effectiveness in problem identification and resolution.

Plant Support performance was consistent. The radiation protection, chemistry controls and emergency preparedness programs continued to be effective. Some problems, though, were noted with chemistry not initiating problem evaluation reports into the corrective action program.

Security programs and staff performance continued to be maintained at a satisfactory state of readiness to respond to an event and security equipment continued to be well maintained. The fire prevention program continued to be effectively implemented. Fire barrier penetration seal

. engineering evaluations were well supported by engineering documentation and records. Self-assessments of the fire protection program and security program were both comprehensive and effective. The performance during the period does not warrant any additional inspection effort ,

above the core inspection program. Some increased emphasis will be placed on core inspections of chemistry corrective action implementation.

Enclosure 1 contains a historical listing of plant issues, referred to as the Plant issues Matrix (PIM), that were considered during this PPR process to arrive at an integrated view of licensee performance trends. The PIM includes items summarized from inspection reports or other docketed correspondence between the NRC and the Tennessee Valley Authority. The NRC does not attempt to document all aspects of licensee programs and performance that may be functioning appropriately. Rather, the NRC only documents issues that the NRC believes warrant management attention or represent noteworthy aspects of performance.

This letter advises you of our planned inspection effort resulting from Sequoyah PPR review. It is provided to minimize the resource impact on your staff and to allow for scheduling conflicts and personnel availability to be resolved in advance of inspector arrival onsite. Enclosure 2 details our inspection plan for the next 8 months. The rationale or basis for each inspection outside the core inspection program is provided so that you are aware of the reason for emphasis in these program areas. Resident inspections are not listed due to their ongoing and continuous nature.

We willinform you of any changes to the inspection plan. If you have any questions, please me at 404-562-4530.

Sincerely, (Original signed by Par E. Fredrickson)

Paul E. Fredrickson, Chief Reactor Projects Branch 6 Division of Reactor Projects Docket Nos. 50-327,50-328 License Nos. DPR-77, DPR-79

Enclosures:

1. Plant issues Matrix

2. Inspection Plan

4 b

'IVA '4 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 1 Tennessee Valley Authority l 6A Lookout Place 1101 Market Street I Chattanooga, TN 37402-2801 l Masoud Bajestani I Site Vice President I Sequoyah Nuclear Plant Tennessee Valley Authority P. O. Box 2000 Soddy-Daisy, TN 37379 ,

i General Counsel Tennessee Valley Authority ET 10H

' 400 West Summit Hill Drive Knoxville, TN 37902 Nicholas C. Kazanas, General Manager Nuclear Assurance Tennessee Valley Authority SM Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 l

Mark J. Burzynski, Manager Nuclear Licensing Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 .

cc w/encls continued: See page 5 1 4

.j

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TVA 5 cc w/encis: Continued Pedro Salas, Manager ,

Licensing and Industry Affairs '

Sequoyah Nuclear Plant )

Tennessee Valley Authority .

P. O. Box 2000 '

Soddy-Daisy, TN 37379 -

D. L. Koehl, Plant Manager Sequoyah Nuclear Plant Tennessee Valley Authority P. O. Box 2000 Soddy Daisy, TN 37379 -

Michael H. Mobley, Director i Division of Radiological Health l TN Dept. of Environment and l Conservation

!- ~3rd Floor, LNC Annex 401 Church Street Nashville, TN 37243-1532 i

County Executive l Hamilton County Courthouse l Chattanooga, TN 37402-2801 Distribution w/encls: 1 l S. Collins, NRR J. Zwo!inski, NRR H. N. Berkow, NRR l R. W. Hernan, NRR W. M. Dean, NRR T. H. Boyce, NRR J. Lieberman, OE G. M. Tracy, OED A. P. Hodgdon, OGC B. J. Keeling, GPA/CA l W. Bearden, Ril -

C. F. Smith, Ril D. W. Jones, Rll O. H. Thompson, Ril i L. S. Mellen, Ril l PUBLIC -

l-Distribution w/encls continued: See page 6 l

1 1

TVA 6 1

Qistribution w/encls: Continued l NRC Resident inspector, Operations U. S. Nuclear Regulatory Commission 1260 Nuclear Plant Road Spring City, TN 37381 1

NRC Resident inspector i Sequoyah Nuclear Plant U. S. Nuclear Regulatory Commission  ;

2600 Igou Ferry Road Soddy-Daisy, TN 37379 l

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• See previous concurrence - attached OFFICE Rit:DRP Ril:DRS Ril:DRs Ril:DRs Rit:DRs slONATuRE * * * *

• NAME P Taylor att K Landis K Barr H Christensen G Belisle DATE 3/ 199 3/ 199 3/ 199 3/ 199 3/ /99 3/ 19 9 3/ 199 cOf-Y? YES NO YES NO YES NO YES NO YES NO YES NO YES NO OFFICIAL RECORD COPY DOCUMENT NAME: G:\sQ\PPR\PRCOVLTR.WPD

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TVA 6 Distribution w/encis: Continued B. J. Keeling, GPA/CA M. D. Tschiltz, OEDO R. W. Hernan, NRR H. N. Berkow, NRR C. F. Smith, Ril D. W. Jones, Ril D. H. Thompson, Ril L. S. Mellen, Ril PUBLIC NRC Resident inspector, Operations U. S. Nuclear Regulatory Commission 1260 Nuclear Plant Road Spring City, TN 37381 ^

NRC Resident inspector Sequoyah Nuclear Plant -

U. S. Nuclear Regulatory Commission 2600 Igou Ferry Road Soddy-Daisy,'TN 37379 i

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OFFICE Ril;DRP Ril:DW/ RU:DRs RH:DRs y . ps slGNATuRE Vg )M ghV (N fY b NAME P Taylor att - K lam 4,K Sirr H CAristensen G,.( d_ is ( e DATE 3// L 199 ,$ 199 3//L 199 m /3k199 _3(f[,199 31 199 3/ 199

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(N United States Nuclear Regulatory Commission PLANT ISSUES MATRIX

( . . .* by SALP Functional Area SEQUOYAH 19-Mar /s9 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES F m wm&+pj 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 dusing the Unit 2 startup.

A 00000 B B0000 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 0G000 a00000 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 0G000 s00000 cO 000 9/18/98 Negative IR98-08 NRC Operators failed to identify an incorrect control room log 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 g00000 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 fuel.

A 00000 gD0000 cO 000 8/4/98 Positive OPS IR 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 0000G B 00000 cO 000 FROM: 2/22/98 TO: 1/31/99 Page 1 of 16 FOR PUBLIC RELEASE Last Updated: 9/18/98

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SEQUOYAH 19-Mar-99 DATE TYPE (s) SEC.SFA SOURCE (s) !D'd ISSUE (s) SMM CODES 8/4/98 Positive OPS tR 98-07 NRC Shift turnovers and mid-shift briefings continue to be effective in supporting plant 1 234 5 operations .

A00000 g00000 c0 000 6/26/98 Positive IR 98-06 NRC A positive finding was identified ln that the licensee responded promptly and 1234 5 appropriately to an essential raw cooling water leak inside the Unit 1 annulus which had rendered a radiation monitor containment isolation valve inoperable. AOOOOO B 00000 cO 000 6/26/98 Positive IR 98-06 NRC The inspector concluded that the licensee has implemented compensatory actions 1 234 5 to address the issue of part length control rod drive mechanism potential cracking.

A 00000 B 00000 cO 000 6/26/98 Negative iR 98-06 NRC The inspector identified a negative finding when operators failed to loca!!y monitor 1 234 5 the Unit 2 TDAFW pump during a maintenance run of the pump.

A00000 B 00000 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-iound condition of a valve that had failed to fully stroke. A BOOOO g00000 cO 00O

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6/26/98 Positive IR 98-06 NRC Operators performed well in addressing the degrading plant conditions prior to the 1 234 5 automatic reactor trip and performing the subsequent recovery actms A00000 aG0000 cO 000 5/15/98 Negative IR 98-04 NRC The inspectors observed water dripping from the vita! 13-B emergency raw cooling 1 234 5 water system 480 volt ac motor control center. This adverse condition had not been identified by the licensee. AOOOOO s00000 cO 000 FROM: 2/22/98 TO: 1/31/99 Page 2 of 16 FOR PUBLIC RELEASE Last Updated: 9/18/98

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SEQUOYAH 19-Mar-99 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 9/18/98 Positive IR98-08 NRC The Scensee'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 B 00000 cO 000 9/18/98 Positive IR98-08 NRC The licensee implemented a well-planned forced outage schedule following the Unit 1 234 5 2 trip on August 27.

A 00900 B 00000 cO 000 8/4/98 Negative PLT GUP IR 98-07 LICENSEE A craftsman did not adequately understanding the effects of installing test 1234 5 equipment on operating plant equipment when measuring the output frequency of the uninterruptable power supply (UPS), consequently the UPS power supply breaker trip and resulted in the partial loss of the site security system.

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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 activities for systems, structures and components within the scope of the Maintenance Rule.

A OOOOG 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 s00000 c0 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 00B00 sD0000 cO 000 6/26/98 Strength IR 98-06 NRC A strength was identified in that eddy current data evaluation and management tools 1 234 5 were strong components of the licensee's program for steam generator degradation management- A OOOOO B 00000 c0 000 FROM: 2/22/98 TO: 1/31/99 Page 5 of 16 FOR PUBLIC FIELEASE Last Updated: 9/18/98 s

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SEQUOYAH 19-Mar-99 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 6/12/98 Strength IR 98-05 NRC The team found that the licensee's root cause determinations and corrective actions 1 234 5 met the requirernents of Criterion XVI. The inspectors considered the analysis conscientious, self critical and a good example of a thorough root cause analysis. A OOOOO B 00000 cO 000 6/12/98 Positive IR 98-05 NRC The inspectors found that procedure for commercial grade dedication provided 1234 5 adequate guidance for the procurement and dedication of w mmu,io; grade material with minor exceptions. A OOOOO a00000 CO 000 6/12/98 Weakness IR 98-05 NRC The vendor interface program was in coraert with the NRC position. The team 1 234 5 identified a lack of a vendor manua! for the Type DB-25 circuit breakers.

A 00000 B OOGOO 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 B 00000 c0 000 6/12/98 Positive IR 9845 NRC The team found the licensee was complying with 10 CFR 50.65 Maintenance Rule 1 234 5 tvith regard to treatment of power circuit breakers.

A 00000 B 00000 c0 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 s00008 CO 000 E/12/98 Positive MAINT IR 98-05 NRC The team's review of maintenance records for ten safety-related circuit breakers 1234 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 oventue PMs.

A OOOOO O000O c0 000 FROM: 2/22/98 TO: 1/31/99 Page 7 of 16 FOR PUBLIC RELEASE Last Updated: 9/18/98

SEQUOYAH 19-Mar-99 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) ,

SMM CODES 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 maintentnce procedures were considered a strength. A OOOOO aO0000 cO 000 6/13/98 Positive IR 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 B 00000 c0 000 5315/98 MISC IR 98-04 NRC A concem was identified with the process for rardomly sampling of the ice 1 234 5 condenser ice basket weights due to approximately one third of the ice baskt.ts in the Unit 1 and a lesser percentage of baskets in the Urr. 2 ice condenser, being A O O O O O.

frozen in place.

sOOOOO cO 000 5/15/98 Positive IR 98-04 NRC, Based on a random visual check of the Unit 1 ice condenser, it appeared that the 1 234 5 licensee'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 cO 000 4/6/98 Positive IR 98-03 NRC The corrective action program was generally implemented in aw da 6 witn 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

• confonning conditions and fully satisfied the requirements of 10 CFR 50 Appendix B A OOOOO

, Critorion XVI. B OOOOO cO 000 4/6/98 MISC IR 98-03 NRC The inspectors noted that the licensee's ASME Section XI valve testing program 1 234 5 may not include all necessary/ required valve testing and further review will be necessary to resolve this issue. A OOOOO B 00000 cO 000 FROM: 2/22/98 TO.1/31/99 Page 8 of 16 FOR PUBLIC RELEASE Last Updated: 9/18/98

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SEQUOYAH 19-Mar-99 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 6/26/98 Positive IR 99-06 NRC Coservation of pump tests , review of pump test proceoures, and review of pump 1 234 5 parameter trend data indicated the licensee has established and implemented an adequate pump IST program. A OOOOO B 00000 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 gerwrator hydraulic snubber leak was property assessed for operability and a thorough corrective action plan was promptly A OOOOO

"P'*"'*"'*d' sOOOOO cO 000 6/26/98 Weakness IR 98-06 NRC A weakness was identified due to coritinuing steam dump system problems which 1 234 5 resulted in the May 19,1998 water hammer event and piping support damage.

A 00000 B 00000 cO 000 6/26/98 Positive . IR 98-06 NRC A positive finding was losntified based on system Engineering successfully 1 234 5 developing and implementing an action pian to remove boron from the Unit 1 lower compartment coolers. A OOOOO B 00000 cO 000 EE6/98 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 B 00000 c0 000 5/15!98 Positive IR 98-04 NRC The licensee has taken appropriate corrective actions to periodically monitor and 1 234 5 refurbish reactor protection system power supplies, A 00000 s00000 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 fe4 towing items: potential failure to meet the UFSAR requirements for having an automatic gas analyzer, not adequately revising the UFSAR, inappropriately closing

.OOOOO the design change pacakage, and not establishing a periodic oxygen /tryogen B OOOOO sampiing pmgram.

cO OOO FROM: 2/22/98 TO: 1731/99 Page 10 of 16 FOR PUBLIC RELEASE Last Updated: 9/18/98

SEQUOYAH 19-Mar-ss l

DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 3G0/98 MISC IR 98-01 NRC A concem was identified related to an ur. verified FSAR chapter 15 Accident Analysis 1234 5 assumption for 10 minute operator action on a main feedwater piping rupture.

A 00000 s30000 cO 000 300/98 Weakness SAQV IR 98-01 NRC A weakness was identified for engineenng's poor independent review of calculations 1 234 5 and technical evaluations which failed to identify errors.

A 00000 B 00000 cO 000 3f30!98 Strength SAQV 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 s00000 cO 000 3G0/98 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 3G0/98 Weakness IR 98-01 LICENSEE A weakness was identified in implementation of the design control program based 1 234 5 on inadequate engineering calculations and inconsistency in design basis documents. A OOOOO B 00000 cO 000 3/D/98 Positive IR 98-01 NRC A positive finding was identified in connection with the AFW system as installed 1 234 5 configuration and operating instructions, both of which met tha original design basis and subsequent licensing commitments as demonstrated by TS changes 89-03 and A OOOOO s000OO cO 000 3/D/98 Positive IR 98-01 NRC A positive finding was identified conceming the operational performance c oability of 1 234 5 the AFW system. The motor driven AFW pump motors were adequately si.ed and were capable of performing their design functions under t"e most limiting conditions of 153 KV on the 161 KV switchyard bus.

A OOOOO OOOOO cO 000 F m~=gWWc ; q]

FROM: 2/22/98 TO: 1G1/99 Page 11 of 16 FOR PUBLIC RELEASE Last Updated: 9/18/98

SEQUOYAH #9-Mar-99 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 Emergerm/; 1 234 5 Plan drill.

A 00000 s00000 c0 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 chemistry control program and secondary water quality were 1 234 5 being implemented in accordance with TS requiements.

A 00000 s00000 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 Dopartment of Transportation regulations.

A 00000 s00000 cO 000 8/4/98 Positive IR 98-07 NRC Radiation work activities were well planned and worker radiation dose were 1234 5 maintained well below regulatory limits.

A 00000 B 00000 cO 000 8/4/98 Positive SAOV 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 cO 000 EI4/98 Positive MAINT IR 98-07 NRC The maintenance and surveillance 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 *34 5 system demonstrated emergency lighting was ope %Ie end correctly aimed to illuminate post-fire alternate shutdown equipment. A OODOO B 00000 cO 000 FROM: 2/22/98 TO: 1/31/99 Page 12 of 16 FOR PUBLIC RELEASE Last Updated: 9/18/98

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SEQUOYAH 19-Mar-99 t

DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES '

4/6/98 Positive SAOV IR 98-03 NRC The inspectors determined the licensee was effectively conducting formal radiation 1 234 5 protection auriits as required by TS and conducting self-assessments. The licensee was effectively developing corrective action plans and completing corrective actions in a timely manner.

A OOOOO OOOOO c0 000 4/6/98 Positive IR 98-03 NRC The meteorological instrumentation had been adequately maintained and the 1234 5 met.c=-@ monitoring program had been effectively implemented.

A 00000 sD0000 cO 000 4/E198 Positive IR 98-03 NRC The water chemistry control program for ne &ning primary and secondary water 1 234 5 quality had been implemented, for those parameters reviewed, in accordance with the TS requirements. A OOOOO s00000 c0 000 4/6/98 Positive IR 08-03 NRC The licensee had effectively implemented a prog am for shipping and receiving 1 234 5 radioactive materials as required by NRC and DOT regulations.

A 00000 s00000 c0 000 4/E!38 Positive iR 98-03 NRC Contamination control was effective. 1 234 5 A 00000 s00000 c0 000 CA/98 Positive IR 98-03 NRC Radiation work activities were planned, radiation worker doses were being 1234 5 maintained wel below regulatory limits and the licensee was continuing to maintain exposures AUiRA. A OOOOO s00000 cO 000 4/E!98 Positive IR 98-03 NRC Radiological facility conditions and housekeeping in radioactive waste storage areas, 1 234 5 health physics facilities, auxiliary building and refueling floor were observed to be good and material was labeled appropriately. A OOOOO s00000 cO 000 FROM: 2/22/98 TO: 1/31/99 Page 15 of 16 FOR PUBLIC RELEASE Last Updated: 9/18/98

SEQUOYAH 19Maf-99 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 4M/98 VIO IR 98-03 NRC A violation was identified for failure to initiate a problem evaluation report after 1 234 5 chemistry 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 blockage of the sample line. B OOOOO cO 000 SMMTemplate Codes: SALP Functional Areas: ID Code:

1A lOPERATIUN PEREURMANCE - Normal Operations UCENSEE l LICENSEE 1B OPERATION PERFORMANCE - Operations During Transients ENG l ENGINEERING NRC ;NRC 1C joPERATION PERFORMANCE - Programs and Processes MAINT MAINTENANCE SEl.F lSELF-REVEALED 2A. , MATERIAL CONDITION - Equipment Condition OPS  ; OPERATIONS -

2B jMATERIAL CONDITION - Programs and Processes PLT SU PLANT SUPPORT 3A ; HUMAN PERFORMANCE - Work Performance SAQV SAFETY ASSESSMENT & QV 3B jHUMAN PERFORMANCE - KSA 3C , HUMAN PERFORMANCE-Work Environment 4A { ENGINEERING / DES!GN - Design l 48 ; ENGINEERING' DESIGN - Engineering Support 4C jENGINEERING/ DESIGN - Programs and Processes 5A ; PROBLEM IDENTIFICATION & SOLUTION - identification 5B l PROBLEM IDENTIFICATION & SOLUTION - Analysis SC ; PROBLEM IDENTIFICATION & SOLUTION - 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 vnakes its enforcement decision, the licensee will be provided with an opportunity to either (1) respond to the apparent violation or (2) requ*st a predecisional enforcement conference.

UR!s are unresolved items about which more information is required to determine whether the issue in question is an acceptable item, a deviation, a nonconformance, or a violation.

However, the NRC has not rest.hed its final conclusions on the issues, and the PIM entries may be modified when the final conclusions are made.

FROM: 2/22/98 TO: 1/31/99 Page 16 of 16 FOR PUBLIC RELEASE Last Updated: 9/18/98

"** *" Date: 03/15/1999 '

United States Nucl:cr Regul:t:ry Comm.er:isn Tim.: 1o:29:2i nooion u PLANT ISSUE MATRIX SEQUOYAH By Dele Funct6cnct Template Date Source Area ID Type Codes item Description 01/02/1999 1998011 Prl: ENG NRC POS Pri: 4C Ice Condenser modrfications were property evaluated for conforman to the Updated Final Safety Analysis Report (UFSAR) description of the system and required changes to the UFSAR were implemented. The hcensee appropnate!y Sec: Sec: initiated changes to the UFSAR where clanfications were needed based on self-assessments and recent analyses Tm (Section E3.1).

01/02/1999 1998011 Prl: MAINT NRC MISC Pri:2A Until all the breakers in the plant have been inspected and tested to the new breaker program requirements, their reliability and affect on plant performance remains a concern (Section M8.1).

Sec: See:

Ter:

01/02/1999 1998011 Pri: MAINT NRC POS Prl:2B The 'icensee made significant improvements in the breaker testing and maintenance program from April - December 1295 iSection M8.1).

Sec: Sec:

Ter:

01/02/1999 1998011 Pri: MAINT NRC POS Pri: 3A The licensee successfully implemented a design ct' Ange to replace the batteries on all Emergency Diesel Generators (Sedion M2.1).

Soc: Sec:

Ter:

01/02/1999 1998011 Pri: OPS NRC NEG Pri: 1C With respect to the TS 3.0.3 violation, licensee management did not provide sufficient guidance to operators conceming performance of channel checks on Reactor Coolant System (RCS) loop flow instrumentation when it was known that the Sec: Sec: Loop 1 instruments were reading high on scale or bouncing above the top of scale (Section O1.3).

Ter:

01/02/1999 1998011 Pri: OPS NRC NEG Pri: 3A Wrth respect to the TS 3.0.3 violation, the licensee incorredly entered TS 4.0.3 whe't the Surveillance Roquirements requirements of TS 4.3.1.1.1 could not be performed (Section 01.3).

Ter:

01/02/1999 1998011 Prl: OPS NRC NEG Prl: 3B With respect to the TS 3.0.3 violation, operators did not challenge the fact that Unit 1 Loop 1 RCS flow indicators had been dnfting high making a valid channel check drfficult to perform when the three indicators routinely indicated greater Sec: Sec: than 110%, the top of the calibrated instrument scale (Section 01.3).

Ter:

01/02/1999 1998011 Pri: OPS NRC POS Prl:3A Assistant Unit Operators performed their routine rounds in a thorough and professional manner (Section 01.2).

Sec: Sec:

Ter:

01/02/1999 1998011 Prt: OPS NRC POS Pri: 1A Based upon a detailed walkdown of acmssible portions of Unit 1 Train A Safety injedion System, the espectors concluded that the system was operable and being maintained in an acceptable material condition (Section O2.1).

See: MAINT See: 2A Ter:

ltem Type (Compliance, Followup,Other) From 02/22/1998 To 01/31/1999

Page: 2 of 8 Date 03/15/1999 United States Nucle:r Regul tary Commci";n Tim.: 50:29:2i Region il PLANT ISSUE MATRIX SEQUOYAH By Date Functional Template Date Source Area ID . Type Codes item Description 11/21/1998 1998010 Pri: ENG NRC POS Prl:2B The licensee's engineering requirements for control of borated water extemal corrosion met the requirements of Generic Letter 88-05 (Section EB.2).

Sec: See:

Ter:

11/21/1998 1998010 Prl: ENG NRC POS Pri: 5B The engineering risk evaluation regarding boric acid contamination on the exterior of the Unit 1 pressunzer was sound and conservative (Section E8.2).

Sec: Sec:4B Ter:

11/21/1998 1998010 Pri: MAINT NRC NEG Pri: 2B An NCV was identified for failure to follow procedure during maintenance activities on a diaphragm valve which resulted in an unplanned RCS boron dilution (Section M2.1).

Sec: Sec: 3A Ter:

11/21/1998 1998010 Pri: MAINT NRC POS Frt:2B The stator core windings for emergency desel generators 18-B and 2B-B were not expenencing resistance increases of I a magnitude that would result in an unsatisfactory functional performance (Section M8.1).

Sec: Sec: 2A >

Ter:

11/21/1998 1998010 Prl: MAINT NRC POS Pri: 2B The licensee conducted a thorough root cause evaluation of the Unit 1 dilution svent and initiated corrective actions to address mis-adjustment of diaphragm valves on other plant systems (Section M2.1).

Sec: Sec: 3B Ter:

11/21/1998 1998010 Pri: OPS NRC POS Pri:tg Operators routinely demonstrated awareness, effective plant control, and management of transient conditions during a

• period which was characterized by a power ascension following the Unit 1 Cycle 9 refueling outage Operators routinely Sec: Sec: 1C demonstrated awareness, effective plant control, and management of transient conditions during a period which was characterized by a power ascension following the Unit 1 Cycle 9 refueling outage and two reactor tnps with subsequent unit restarts (Section 01.1).

11/21/1998 1998010 Pri: OPS NRC POS Prl:1B Operators and automatic plant systems controls maintained plant parameters within safety limits following a challenging Unit 1 reactor tnp resulting from the loss of one channel of vital instrument power (Section 01.5).

Sec: Sec: 2A  ;

Ter: ,

11/21/1998 1998010 Pri: OPS NRC POS Prl:1C The licensee has impierrNnted and maintained an adequate freeze protection program (Section O2.1).

Sec: Sec: i Ter:

11/21/1998 1998010 Prl: OPS NRC WK Pri:1A Operators failed to promptly validate Unit 1 reactor coolant system (RCS) chemistry samples who resulted in a delay in identifying an ongoing dilution event (Section M2.1) >

Sec: See: 1C Ter:

mem Type (Compliance, Followup.Other). From 02/N1tr38 To 01/31/1999

Page: 3 of 8 Date: 03tt5/1999 Urdted States Nucirr Regul:tsiy Cortiiviiririti Time: 50 29:21 Region 11 PLANT ISSUE MATRIX SEQUOYAH By Date Functional Template Date Source Area ID Type Codes item Description 11/21/1998 1998010 Pri: OPS NRC WK Pri:1B During the Unit 1 trip, operators were unaware that the steam generator safety va!ves were cycling continuous!y for a pen'od of seventeen minutes due to a malfunction of the steem generator atmospheric refef valves (Section O1.5).

Sec: Sec:

Ter-11/21/1998 1998010-03 Pri: MAINT Licensee NCV Pri:3A An NCV was identified for failure to follow procedure during maintenance activities on a diaphragm valve which resulted in an unplanned RCS boron dilution (Section M2.1).

Sec: Sec: 2B Ter:

11/20/1998 1998015 Pri: PLTSUP NRC POS Pri:1C The licensee conducted security and safeguards activities in a manner that protected public health and safety and that this portion of the prograrn, as implemented, met the licensee's commitments and NRC requirements.

Sec: Sec:

Tor, 11/20/1998 1998015 Pri: PLTSUP NRC POS Prl: 1C The licensee's secunty facihties and equipment were determined to be well maintained and reliable. The excellent engineering and instrumentaten and control personnel support was the major contnbuting factor to continued Sec: Sec: operability of the detection and assessment equipment. (Section S2).

Ter:

11/20/1998 1998015 Pri: PLTSUP NRC POS Pri: 2B The licensee's actions to implement NRC Information Notice 98-35. Threat Assessments and Consideration of Heightened Phvsical Protection Measures, dated September 4,1998, were reviewed and considered adequate.

Sec: Sec: (Section S4).

Ter:

11/20/1998 1998015 Pri: PLTSUP NRC POS Pri:3B The SFMs adequately demonstrated that they have the requisite knowledge necessary to effectively implement the duties and responsibilities associated with their day-to-day and contingency response postitions.

Sec: Sec:

Ter:

11/20/1998 1998015 Pri: PLTSUP NRC POS Pri: 5A The licensee had implemented an effective audit /self assessment program. Audit findings were reviewed at the appropriate level to assure that corrective actions were implemented on a timely basis and that the corrective action Sec: Sec: was effective (Section S7).

Ter:

11/06/1998 1998014 Pri: PLTSUP NRC POS Pri:1C The NRC team observed the licensee's response in the Control Room Simulator (CRS), the Technical Support Center (TSC), the Operational Support Center (OSC), and the Central Emergency Control Center (CECC). Based on the Sec: Sec: performance observed, the team concluded that the licensee successfully demonstrated its ability to implement the Tm Emergency Plan and implernenting Procedures. (Section P4.0) 10/16/1998 1998013 Pri: ENG NRC POS Pri:4C The licensee's program for monitoring IC 6 wer plenum floor movement was thorough and assured lower inlet door operability. (Section E2.1).

Sec: Sec:

Ter:

ltem Type (Compliance, Followup,Other), From 02/22/1998 To 01/31/1999

Page: 4 of 8 Cate: 03/15/1999 WW mte hdn Rgul ton Comm.el:ri Time: $0:2s:2i Region Il PLANT ISSUE MATRIX SEQUOYAH By Date "

Functional Template Date Source Area ID Type Codes item Description 10/16/1998 1998013 Pri: ENG NRC POS Pri:SA A generally thorough IC self-assessment was noted and independent assessments of IC activities were thorough.

(Section E7.1).

4 Sec: Sec:

Ter:

8 10/16/1998 1998013 Pri: ENG NRC POS Pri:5B A review of problem evaluation reports issued since 1992 showed that licensee evaluations of IC problems for 10 CFR 50.73 reportability were performed adequately. (Section E4.1).

Ter:

10/16/1998 1998013 Pri: MAINT NRC POS Pri:2B The licensee had pvvided reasonable controls for debris in the IC and was thoroughty documenting and adequately evaluating debris which could not be removed (Section M1.2). Appropriate control of IC screws was noted. (Section Sec: See: M2.5). Lower plenum inspections found adequate housekeeping. (Section M2.6)

Ter:

10/16/1998 1998013 Pri: MAINT NRC POS Pri:2B A review of nine IC surveillance procedures showed that the procedures were clearty written and met Technical Specification (TS) requirements. (Section M3.1). Eight surveillances disclosed that IC survei!!ance usults met Sec: Sec: procedural and TS requirements. (Section M3.2).

Ter:

10/16/1998 1998013 Pri: MAINT NRC POS Prt:2B Field observations of Unit 1 IC outage activities found that personnel followed procedures during ice weighing and servicing activities. Thorough oversght of contractor activities was noted during these evolutions. (Section M1.1).

See: Sec: 3A Ter:

10/16/1998 1998013 Pri: MAINT NRC POS Pri:2B The licensee effectively completed the replacement of one damaged basket and effectively conducted an operability determination for 51 Unit I damaged ice baskets. (Section M2.3) As-left ice flow blockage was noted in rows 8 and 9 Sec: Sec:4B which was found to be acceptable by the NRC. (Section M2.6)

Ter:

10/16/1998 1998013 Pri: MA!NT NRC WK Pri:2B An NRC review of the licensee's operability determination was identified as a continuation of an existing Unresolved item (URI). (Section M2.3) A high number of frozen baskets challenged the ability of the licensee to obtain a Sec: Sec: representative sample required by TS. NRC review of this issue was identifW as a continuation of an existing URI.

Tm (Section M3.3).

10/16/1998 1998013-01 Pri: MAINT NRC NCV Pri:2B The licensee failed to properly tape IC upper blankets leading to a licensee-identified, non-cited violation.(Section M2.1).

See: Sec:

Ter:

10/16/1998 1998013-02 Pri: MAINT NRC VIO IV Prt: 3A Intermediate deck door surveillances were property performed, however, intermediate deck door hold 0Jwn bolts were improperly configured on Unit 2 resulting in an NRC identified violation. (Section M21)

Sec: Sec: i Ter: '

Item Type (Compliance, Followup,Other), From 02 '998 To 01/31/1999

P 5 of 8 Date: 03/15/1999 United States Nucirr Regul:ttry Comm,em.n umen0:2ezi Region il PLANT ISSUE MATRIX SEQUOYAH By Date Functional Temp!4ite Date Source Area ID Type Codes item Description 10/16/1998 1998013-03 Prl: MAINT NRC NCV Pri: SA The licensee's technique for servicing ice baskets contibuted to many baskets freezing in-place, resulting in damage to ice baskets occurnng during ice basket servicing. A licensee-identified non-cited violation (NCV) was identifed for the Sec: Sec: SC failure to promptly identify and correct damaged rce baskets. (Section M2.3) Obtaining weight measurement was performed with considerable difficulty or not possible ca many baskets due to baskets being frozen to lattice framework Ter:

(Section Mt.1) 10/16/1998 1998013-04 Prl: MAINT NRC URI Pri:2B The licensee's use of thermal drilling appeared to increase the ice density beyond that expected from normalice-use compaction. A URI was identified to review the licensee's evaluation Of this issue. (Section M2.4) Ice voiding was Sec: Sec: 5B noted and a URI was identifed to review the licensee's evaluation of this issue. (Section M2.6)

Ter:

10/10/1998 1998009 Pri: ENG NRC MISC Pri: SC The licenset determined that close monitoring of unidentified leakage was an acceptable compensatory measure to startup r.nd operate Unit 1 for one operating cycle with dried boron on the exterior of the pressurizer.

Sec: Sec: 2A Ter:

10/10/1998 1998009 Pri: MAINT NRC POS Prl:2B Maintenaace personnel contnbuted to the overa!! success of the Unit 1 Cycle 9 refueling outage by implementing several significant plant modifications and completing a well planned outage schedule.

Sec: Sec:

Ter:

10/10/1998 1998009 Pri: MAINT NRC POS Pri:2B Corrective actions following the failure of a Westinghouse Type DS-532 480 Vac circuit breaker have brought significant improvements to the Type DS Breaker maintenance program.

Sec: Sec:

Ter:

10/10/1998 1998009 Pri: MAINT NRC POS Pri:2B The licensee's implementation of Steam Generator and Inservice inspection programs were thorough and done in a very professional manner. The steam generator eddy current testing program expanded the state-of-the-art by Sec: Sec: implementing a depth-sizing procedure for Primary Water Stress Corrosion Cracking.

Ter:

10/10/1998 1998009 Pri: OPS Licene- NEG Prl:1A Operators overloaded the 1 A-A EDG for less than 30 seconds when they failed to use all available instrumentation.

The engineering evaluation of the EDG overload event concluded that the short duration overload was insignificant.

Sec: Sec:

Ter:

10/10/1998 1998009 Pri: OPS NRC NEG Pri:1A A non-conservative operator action was observed when a heater drain pump was operated in excess of the maximum allowed running current for 40 minutes.

Sec: Sec:

Ter:

10/10/1998 1998009 Pri: OPS NRC POS Pri:1A Operational performance during the Unit i plant shutdown, outage, reduced inventory operation and startup was good and contnbuted to a successful 29 day refueling outage.

Sec: Sec:

Ter:

it;m Type (Compliance Followup,Other), From 02/22/1998 To 01131/1999

. _ . . _ _ _ _ __ . _ . . _ _ _ _ _ _ _ _ _ _ _ . . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . __._m __ __. _ __ ,

Page:- 6 of 8 Date: 03/15/1999 United States Nucizr Regul;.tsry Comm.mion um.: ia:29:21 Region il PLANT ISSUE MATRIX

-SEQUOYAH By Date Functional . Template Date Source Area ID Type Codes item Description 10/10/1996 1998009 Pri: PLTSUP NRC POS Prl: 1C Radiological controls during the UIC9 outage were effective as evidenced by a record low total dose for Unit 1 of 200 rem. Maxirnum indrvidual radiation exposures were controlied to levels which were well within the licensee's Sec: Sec: administratrve limit and the regulatory timds for occupational dose speofied in 10 CFR 20.1201(a). The Licensee was genera!!y successful in meeting established Al. ARA goals.

Tm 10/10/1998 1998009 Prl: PLTSUP NRC POS Prl:1C The licensee had implemented an effective shutdown chemistry control plan and closely monitored primary coolant chemistry during the shutdown for the Unit 1 refueling outage.

Sec: Sec:

Ter:

10/10/1998 1998009-01 Pri: MAINT NRC VIO IV Prl:2B A violation was identified with two examples of failure to meet 10 CFR 50, Appendix B, Cnterion XI, Test Control, when Type DS-532 480 Vac circuit breakers failed to perform satisfactorily in service. (Section M2.1)

Sec: Sec:

Ter:

10/10/1998 1998009-03 Pri: ENG NRC URI Prl:4B A concem was identified for the potential failure to property categorize a maintenance preventable functional failure.

(Section E2.2)

Sec: Sec:

Ter:

08/14/1998 Pri: Licensee LER Pri:

See: See:

Ter:

08/14/1998 Pri: Licensee LER Prl:

Sec: Sec:

Ter:

08/07/1998 1998012 Prl: PLTSUP NRC POS Pri:1C Implementation of the Access Authorization and Fitness For Duty programs at the Corporate Off:ce was excellent. The licensee had currer tly implemented and staffed an organization that was capable of managing and implementing the Sec: Sec: program requirements (Section St.2.1)

Ter:

08/07/1998 1998012 Pri: PLTSUP NRC POS Prl: 1C The licensee appropriately followed implementing procedures with respect to the appeal process and met the requirements of 10 CFR 73.26 and 73 56. (Section S1.2.3)

See: Sec:

Ter:

08/07/1998 1998012 Pri: PLTSUP NRC POS Pri: 1C The licensee's sites were currently capable of continuing to provide high assurance that the personnel who were granted unescorted access to the nuclear facilites met regulatory requirements. (Section St.2.2)

Ter:

Item Type (Compliance, Followup Other), From 02/22/1998 To 01/31/1999

Page: 7 of 8 - Date: 03/1$/1999 United States Nucle 2r Regul: tory Comm*iscion ume:io:29:2i Region 11 PLANT ISSUE MATRIX SEQUOYAH By Date Functional Template Date Source Area ID Type Codes item Description

' 08/07/1998 . 1998012 Prl: PLTSUP NRC. POS Pri:1C The Fitness for Duty organization and management control systems met regulatory requirements. Personnel were aware of their individual responsibilities and were trained to perform their intended functions. (Section S1.3.1)

Sec: Sec: 38 Ter:

08/07/1998 1998012 Pri: PLTSUP NRC STR Prl: 1C Audits were complete and effective in terms of uncovering weaknesses in the programs, procedures, and practices.

Audd items were reviewed, appropriately assigned, analyzed, and prioritized for corrective action. Corredive actions Sec: See: 5B were technically adequate and performed in a timely manner. The Access Authorization and Fitness For Duty audits were considered a strength (Section St.32)

Tm P

l ftem Type (Compliance, Followup,Other), From 02/22/1998 to 01/31/1999

Page: S of 8 . Date: 03/1:11999 United States Nuclear Regulit:ry Comm.ers;ri rim.: iom:21 PLANT ISSUE MATRIX

- By Date Legend Type Codes: Template Codes: Functional Areas:

BU Bulletin riA NormalOperatens ' OPS ~ Operations I CDR Construction 1B Operations During Transients MAINT Maintenance DEV Deviation 1C Programs and Processes ENG Engineering EEI Escalated Enforcement item 2A Equipment Condition PLTSUP Plant Support IFl Inspector follow-up item 2B Programs and Processes OTHER Other t

LER Licensee Event Report 3A Work Performance LIC Licensing Issue 3B KSA MISC Miscellaneous 3C Work Environment MV Minor Violation 4A Design NCV NonCited Violation 4B Engineering Support NEG Negative 4C Programs and Processes NOED Notice of Enforcement Discretion SA identification NON Notice of Non-Conformance 5B Analysis P21 Part 21 e

5C Resolution POS Positive ID Codes:

SGI Safeguard Event Report _

'NRC NRC'~

STR Strength Self Self-Revealed URI Unresolved item Licensee Lk:ensee VIO Violation WK Weakness 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 Achon"(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.

URis are unresolved items about which more information is required to determine whether the issue in queshon is an acceptable item, a deviation, a nonconformance, or a violation. A URI may e Iso be a potential vio:ation that is not likely to be considered for escalated enforcement action. However, the NRC has not reached its final conclusions on the issues, and the PIM entnes may be modified when the final conclusions are made.

Item Type (Compliance, Followup,Other), From 02/22/1998 To 01/31/1999

. . , - . _ _ . _ . . _ . . _ . - . . _ _ _ _ . ~ . _ . _ . _ . . __ _ _ _ _ . . _ _ . _ ._ m _

i SEQUOY4H INSPECTION PLAN .  ;

Inspection Title inspectors inspection Type of Inspection I Procedures Dates  ;

IP 71001 Ucensed Operetor Re-qualification 2 8/99 Core: Emphasis on licensed operator performance of ,

Program Evaluation EOPs during evaluation of simulator scenarios. l lP 73753 Inservice Inspection (ISI) 1 5/99 Core IP 62700 Maintenance Practices 1 5/99 Regional Initiatives: (1) Emphasis on breaker program  :

1 5/99 maintenance and post maintenance testing following  ;

refurt>ishment and (2) ice condenser material conditions  !

during Unit 2 RFO. .

IP 37550 Engineering 3 9/99 Core: Emphasis on design engineering and engineering  ;

support effectiveness in problem identification and  ;

resolution.

IP 83750 Occupational Rad Exposure 1 '5/99 Core Inspection at the facility 2 6/99 Core: Inspection at TVA corporate offices to review i

personnel dose records and programs. 1

. I IP 84750 Rad Waste Treatment Effluent & 1 3/99 Core ' i IP 86750 Environmental Management Solid Radwaste Management &  !

Transport Rad Materials IP 84750 Rad Waste Treatment Effluent & 1 10/99 Core IP 86750 Environmental Management Solid Radwaste Management &

Transport Rad Materials IP 81700 Physical Security Program 1 4/99 Core 1 9/90 -

IP 82701 Operational Status of EP Program 1 6/99 Core Enclosure 2  !

i i

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