ML20196D103

Advises of Planned Insp Effort Resulting from Insp Planning Meeting Held on 981102.Details of Insp Plans Through March 1999 & Historical Listing of Plant Issues,Called Plant Issues Matrix Encl

ML20196D103
Person / Time
Site:	Browns Ferry
Issue date:	11/16/1998
From:	Christensen H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Scalice J TENNESSEE VALLEY AUTHORITY
References
NUDOCS 9812020157
Download: ML20196D103 (28)

Text

I I

i November 16, 1998 Tennessee Valley Authority ATTN: Mr. J. A. Scalice Chief Nuclear Officer and i Executive Vice President 6A Lookout Place ,

1101 Market Street Chattanooga, TN 37402-2801

SUBJECT:

INSPECTION PLAN - BROWNS FERRY

Dear Mr. Scalice:

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 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 planning meeting. We have provided it to minimize the resource impact on your staff and to allow for scheduling conflicts and personnel availability to be resolved before the inspector's arrival onsite. Enclosure 1 details our inspection plan through March 1999. We have provided the rationale or basis for each inspection outside the core inspection program 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.

During this scheduling cycle, we will continue to focus some of our discretionary inspection effort on the resolution of open inspection items. Therefore, we may conduct additional inspections, which are not iisted on Enclosure 1, to close open inspection items that are ready to be resolved. We will notify you at leust 3 weeks before the start of these inspections.

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 i

between the NRC and Browns Ferry. This material will be placed in the public document room. /

/

9812020157 981116 PDR G ADOCK 05000259 PDR l

# 01

l TVA 2 1

We willinform you of any changes to the enclosed inspection plan. If you have any qyestions, I please contact Harold Christensen at (404) 562-4530.

Sincerely, i

(Original signed by Harold O. Christensen)

Harold O. Christensen, Chief Reactor Projects Branch 6 .

Division of Reactor Projects l

Docket Nos. 50-259,50-260,50-296 Ucense Nos. DPR-33, DPR-52, DPR-68

Enclosures:

1. Inspection Plan

2. Plant Issues Matrix 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 j Chattanooga, TN 37402-2801 Karl W. Singer Site Vice President ,

Browns Ferry Nuclear Plant Tennessee Valley Authority P. O. Box 2000 Decatur, AL 35609 General Counse!

. Tennessee Valley Authority ET 10H 400 West Summit Hill Drive i Knoxvi!!e, TN 37902 cc w/encls continued: See page 3

. . . __ . . . _ _ _ . . . ._ . . _ _. . _ _ _ _ _ _ ~ . ._

l TVA 3 L

!, cc w/encls: Continued l Raul R. Baron, General Manager ,

! Nuclear Assurance.

l Tennessee Valley Authority i

SM Lookout Place 1101 Market Street l Chattanooga, TN 37402-2801 f

Robert G. Jones, Plant Manager f Browns Ferry Nuclear Plant l -Tennessee Valley Authority 4 i P. O. Box 2000 l Decatur, AL 35609 '

L Mark J. Burzynski, Manager i Nuclear Licensing l E Tennessee Valley Authority

! 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 -

Timothy E. Abney, Manag'er Licensing and Industry Affairs Browns Ferry Nuclear Plant

. Tennessee Valley Authority l P. O. Box 2000 i

! Decatur, AL 35609 Chairman Limestone County Commission 310 West Washington Street i Athens, AL 35611 i i State Health Officer Alabama Department of Public Health 434 Monroe Street i Montgomery, AL 36130-1701 Distribution w/encls:

L. R. Plisco, Ril H. Christensen, Ril 1 L. Raghaven, NRR j

- A. DeAgazio, NRR F. J. Hebdon, NRR

R. P. Carrion, Ril P. A. Taylor, Ril J

Distribution w/encls continued: See page 4

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Distribution w/encis: Continued i T. K. Morrissey, Ril W. C. Bearden, Rll C. F. Smith, Ril i- E. D. Testa, Ril  :

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, D. H. Thompson, Ril i l L. S. Melien, Ril

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l NRC Senior Resident inspector ,

U. S. Nuclear Regulatory Commission 10833 Shaw Road Athens, AL 35611 l l l

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I SIGNATURE W MV7 / /M (3/A l[-y4L4/\ 7g l NAME R farrion alt K Landis P Fr h rfc 4 G BMelel K Barr T Peebles ,

E DATE ,11/lo /98 11/ )$198 V1/6/98 M/[j/98 ,11// A/98 11//h/98 11/ /98 f

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COPY? / yds / ' NO YES NO YES NO (YEs NO NO YES NO I

OMAL RECORD COPY DOCUMENT NAME: G:\BhLKr6ERS\PPRBF.LTR U r

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i BROWNS FERRY INSPECTION PLAN INSPECTION TITLE / PROGRAM AREA NUMBER OF PLANNED TYPE OF INSPECTION -

PROCEDURE / INSPECTORS INSPECTION COMMENTS TEMPORARY DATES INSTRUCTION l?s 93809, SAFETY SYSTEM ENGINEERING 4 PLUS 2 11/98 CORE INSPECTION 37700,37701, INSPECTION TRAINEES 37702,72701 [ ENGINEERING - ENG)

IP 92903 GL 89-10 FOLLOWUP 1 11/98 FOLLOWUP INSPECTION

[ PLANT SUPPORT - Sl]

IPs 93809, SAFETY SYSTEM ENGINEERING 4 PLUS 2 11/98 SSEl CONCLUSION .

37700,37701, INSPECTION TRAINEES INSPECTION 37702,72701 [ ENGINEERING - ENG)

IPs 92903 and ENGINEERING OPEN ITEM 1 11/98 REGIONAL INITIATIVE i 37550 FOLLOWUP .

l

[ ENGINEERING - ENG]

lPs 84750 and EFFLUENTS AND CHEMISTRY 1 12/98 CORE INSPECTION 86750 SOLID RAD WASTE & TRANSP.

[ PLANT SUPPORT - PS]

IP 71001 LICENSED OPERATOR 3 01/99 OPERATOR REQUALIFICATION -

INITIAL EXAMINATION - PREP CORE INSPECTION i

[ PLANT OPERATIONS - OLHP]

t IP 71001 LICENSED OPERATOR 3 02/99 OPERATOR REQUALIFICATION -

INITIAL EXAMINATION CORE INSPECTION

[ PLANT OPERATIONS - OLHP]  ;

Enclosure 1

_ _ , _ , _ _ __ _ .. . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ _ _ ..m.

.w lPs 84750 and EFFLUENTS AND CHEMISTRY 1 02/99 CGRE INSPECTION 86750 SOLID RAD WASTE & TRANSP. ,

[ PLANT SUPPORT - PS]

IP 81700 PHYSICAL SECURITY PROGRAM 1 02/99 CORE INSPECTION

• FOR POWER REACTORS

[ PLANT SUPPORT - Sl]

IP 82701 EMERGENCY PREPAREDNESS 1 03/99 CORE INSPECTION ,

[ PLANT SUPPORT- PS) .

i IP 83750 RADIOLOGICAL EFFLUENTS l 1 04/99 CORE INSPECTION ,

AND CHEMISTRY

[ PLANT SUPPORT - PS)

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Dole:11/13/1996 United States Nuclear Regulatory Commission nme:is:3s:so Roo6on il PLANT ISSUE MATRIX Page:1 ou BROWNS FERRY By Primary Functeos.al Area j Functional Template Date Source Area ID Type Codes llom Description 11/02/1908 1998006 01 Prt OPS Ucensee NCV Prt 1 A A control rod was inodverfently withdrawn severd notches post its previous position and prompfty inserted back to its

, , intended position. The licensee's investigation determined that the cause of the mispositioned control rod was human error and the cause of the re-insertion of the control rod without direction was human error.

Ter-10/03/1998 1998006 Prt OPS NRC NEG Prt 1 A Operations personnel inoppropriately entered into TS LCO 3.0 3 when togging out the Unit 3 CAD system prior to reactor Sec'

• h, '

shutdown for the refueling outage. Although the octual conditions for entry into TS LCO 3.0.3 did not exist, operators involved were not oppropriately sensitive to intentional entry into TS LCO 3.0.3.

Ter-10/03/1998 1998006 Prt OPS NRC NEG Prt IA Ucensee management expectations for signing the working copies of cieorances in the field were not diligently 3, . ~

Implemented, as identified by two examples. The Econsee clearty communicated expectations to Operations r,ersonnel following identrfication of the issue Tec 10/03/1998 1998006 Prt OPS NRC POS Prt IB Ptor .t systems responded as designed when on outomatic turbine trip and reactor scram occurred on Unit 2. Thorough

g. ' g troubleshooting of the stator cooling water system led to prompt identification of the cause. The licensee's incident investigation Team performed a thorough investigotion of the event.

Tec SB 10/03/1998 1998006 Prt OPS NRC POS Prt 2A General materiot conditions of the Unit 2 Core Spray system and of the Unit 3 torus were considered to be good.

Sec: Sec:

Tec 08/22/1998 1998005-02 Prt OPS Licensee NCV Prt1A The licensee identified that a high steam dome pressure indication was not effectively evoluoted to determine W- necessary corrective measures, os required by procedures, when the steam dome pressure was recorded and

' See: 3B determined to be outside of the TS-required acceptance criterio.

Tec 08/22/1998 1998005 Prt OPS NRC POS Prt IA Fue! receipt inspections were performed effectively and demonstrated good ottention to detail.

See:' >

Sec:

Tec item Typs (Compliance.Fo!!owup,Other), From 04/19/1998 To 12/18/1999

United States Nuclear Regulatory Commission - '*$'E'S0 Region il PLANT ISSUE MATRIX Page: 2 oM BROWNS FERRY By Pnmory Functional Area Functional Temploie Dole Source Areo ID Type Codes llem Description 10/03/1998 1098006 Prt MAINT NRC POS Prt 2B The licensee's Inservk:s !c,W.(IST) program scope was satisfactory. The licensee's Program Manual for the second ten-year IST interval was consistent with the ASME Section XI code requirements. The licensee developed and he-* k c.*

implemented procedures which met IST program requirements for reactor core isolation cochng (RCIC) and residud Tec heat removd systems (RHR) were described and tested in oppropriate procedures.

10/03/1998 1998006 Prt MAINT NRC POS Prt 3A Thorough troubleshooting of equipment problems was observed during the inspection period. Workers were found to Sec:

w o&es wee demonshoted.

See: 3B Ter 10/03/1998 1998006 Prt MAINT NRC POS Prt 28 Operators conservatively bocked out of testing and consulted engineering for support when problems were 4

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Sec: ENG Sec:3B '

on in-depth knowledge of the test and the consequences of potentid personnel errors.

Ter: ,

08/22/1998 1998005 Prt MAINT NRC POS Prt 1A Maintenance work activities were performed in a professional and thorough manner Sec: See:

Tec 08/22/1998 1998005 Prt MAINT Ucensee POS Prt IA Effective troubleshooting by licensee engineers determined the cause of on oil foaming problem with the Unit 3 Re ctor Core Isolation Cooling System. Troubleshooting activities were wellplanned and executed with relioble kc- kc M maintenance support.

Tec 11/02/1998 1998006-02 Prt ENG NRC VIO Prt IC Surveillance procedures for functiond testing of the residud heat removal loop 1/11 volve logic and interlocks were Sec: Sec:

hodequ h Tec 11/02/1998 1998006-03 Pri: ENG Ucensee NCV Prt 1A The licensee failed to identify inoperable RBM channels and take the actions specified by Technicd Specification 3.3.2.1 kc- kc.

Tec item Type (Compliance. Followup,Other), From 04/19/1998 To 12/18/1999

Dole: 11/13/1996 United States Nuclear Regulatory Commission nme: iS:3Sso Rosen n PLANT ISSUE MATRIX Page: 3 oM BROWNS FERRY By Primary Functional Area Functional Temploie Date Source Aroo ID Type Codes item Description 10/03/1998 1998006 Prt ENG NRC MISC Prt I A The licensee *s resolution that on Emergency Dierel Generator cooter leck was not a failure was considered to im

g.

• gp incorrect. However, the licensee performed on odequate review to determine the cause of the leak on the 1/2C diesei potor cooler.

Tec 58 10/03/1998 1998006 Prt PLTSUP NRC POS Prk 1 A Tie licen%e property monitored and controlled personnel todotion exposure dunng the Unit 3 Cycle 8 refueling outage

g. nd pusted area radiological conditions in accordance with 10 CFR Port 20. Briefings on radiological hozords and

• Sec: 28 protective measures were adequate. Maximum individual rodiction exposures were well within the regulatory limits for Ter- occupational dose specified in 10 CFR 20.1201(c). The licensee was generolfy successfolin meeting established ALARA goois.

10/02/1998 1998012 Prt PLTSUP NRC POS Prt 1 A The licensee's security facilities and equipment were determined to be very well maintained and relioble. The initiative

g.

• g *, to develop a map of the effective zones of detection and to return the zones to that stotus offer major mainter.once was considered a strength. The excettent Engineering and I&C support was the major contributing factor to continued Tec operability of the detection and assessment equipment.

10/02/1998 1998012 Prt PLTSUP NRC POS Prt 1 A The SFMs adequotely demonstrated that they have the requisite knowledge necessor/ to effectively implement the M Sec, duties and responsibilities associated with their day-toh and contingency response positions.

Tec 08/22/1998 1998005 Prt PLTSUP NRC POS Prt1A The protected creo was well lit and temporary structures had sufficient temporary lighting.

Sec: See:

Tec 08/22/1998 1998005 Prt PLTSUP NRC POS Prt 1A During new fuel receipt, the Radiction Protection technicions performed thorough and consistent surveys and were Sec-knowledgeoble of the new survey requirements.

Sec.

Tec itern Typa (Compliance. Followup.Other), From 04/19/1998 To 12/18/1999

ocoo: unsnm United States Nuclear Regulatory Commission - nm.: is:3s:so --

PLANTISSUE MATRIX "9':4

By Primary Functional Aroo Legend Type Codes: Tempbte Codes: Functional Areas.

BU Bulletin 1A Normd Operations OPS Operations CDR Construction IB Operations During Transients MAINT Maintenance DEV Deviation IC Programs and Processes ENG Engineering eel Esco!ated Enforcement item 2A Equipment Condition PLTSUP Rant Support IFl inspector follow-up item 2B Programs and Processes OTHER Other LER Licensee Event Report 3A Work Performance LIC Licensing issue 38 KSA KSC Mscetioneous 3C Work Environment MV Minor Violation 4A Design NCV NonCited Violation 4B Engineering Support NEG Negotwe 4C Programs and Processes NOED Notice of Enforcemer;t Discretion 5A Identification NON Notice of Non-Conformance 5B Analysis P21 Port 21 SC Resolution POS Positive ID Codes SGI Safeguard Event Report NRC NRC SI"9ID Self Self-Revealed URI Unresolveditem Ucensee L'censee 00 Violation WK Weakness Eels are apparent violations of NRC Requirements that are being considered for escdoted enforcement action in occordancs with the "Generd 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 identifed by the Eels and the PIM entries may be modified when the final decisions are mode.

URts are unresolved items about which more information is required to determine whether the issue in question is on acceptoble itern a devictiort a nonconformance, or a violation. A URI may otso be o potentid violation that is not likely to be considered for escdoted enforcement action. However, the NRC has not reached its find conciusions on the issues, and the PIM entries may be modifed when the find Conclusions are mode.

Item Typ3 (Compliance, Followup,Other), From 04/19/1998 To 12/18/1999

j% United St;te] Nuclear Regul . tory Commirion i } PLANT ISSUES MATRIX

h. . ./ by SALP Functional Area BROWNS FERRY 13-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES

' ~

OPERATIONS' l 7/11/1998 NCV NCV 296/ 98-0441 LICENSEE The licensee's failure to implement the procedure for retuming a loop i Residual 1 234 5 Heat Removal (RHR) pump and heat exchanger to service in an operable loop resulted in an unrecognized entry into a more restrictive Technical Specification Lirniting Condition for Operation. The licensee's corrective actions were adequate.

A OOOOO Core Spray and RHR procedures were enhanced to address a vulnerability while B OOOOO opening normally closed containment isolation valves.

O OOO 7/11/1998 Positive IR 98-04 NRC The control room operators responded correctly to the tripped 3B recirculation pump 1 234 5 and utilized a conservative approach regarding consideration of the power /f!ow conditions. The licensee's use of thermography to assess damage to switchyard ceramic insulators was good.

A OOOOO OOOOO cO 000 6/16/1998 Positive IR 98-03 NRC During observation cf routine operational activities, the inspectors observed good 1 234 5 procedural compliance. Self checking and communications were conducted in accordance with licensee management expectations. A deficienc+; involving nitrogen gas bottle storage in the reactor building was corrected promptfy by the licensee.

A OOOOO Good supervision of a reactor operator trainee was noted during operation of a B OOOOO diesel generator.

O OOO 6/16/1998 NCV NCV 98-03-01 LICENSEE Personnel errors during development and review of a clearance for maintenance 1 234 5 work on a reactor protection system power supply resulted in an inadvertent engineered safety features actuation. A OOOOO B 00000 cO 000 6/16/1998 Positive IR 98-03 NRC The Unit 1 operator and AUOs demonstrated good coordination. communications 1 234 5 and self checking during the Unit 1 residual heat removal system surveillance for Unit 2 operability. The contaminated area inside the Unit 1 drywell access contained an excessive amount of miscellaneous materials.

A CCCCC OOO cO 000 6/16/1998 Positive IR 98-03 NRC During a Unit 3 midcycle outage, the licensee successfully identified leaking fuel 1 23 4 5 assemblies. Strong reactivity controls were administered for control rod manipulations during the subsequent startup- A OOOOO 8 00000 cO 000 FROM.10/1/1997 TO: 11/13/1998 Page 1 of 18 FOR PUBLIC RELEASE Last updated: 7/11/1998

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BROWNS FERRY 13-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 2/12/1998 NCV MAINT NCV 97-12-01 L!CENSEE A licensee identified & corrected non-cited violation was identified involving control 1 234 5 rod drive temperature recorders in the control room. Inadequate procedural guidance resulted in some of the alarm points being inadvertently tumed off. A OOOOO e00000 cO 000 2/12/1998 Positive IR 97-12 NRC The licensee effectivety monitored control room deficiencies. Aggressive goals have 1 234 5 been set to reduce the number of control room deficiencies. Backup Control Panel deficiencies are not included in the control room deficiency list although their importance may warrant increased awareness.

A OOOOO OOOOO cO 000 2/12/1998 Positive MAINT IR 97-12 NRC Control of important plant equipment & systems during the diesel generator outage 1 234 5 for the 12 year maintenance inspection was good. The electrical portion of the 3C diesel generator tagout conservatively used redundant means to ensure equipment was de-energized. One exception to normal site practices was identfied associated A OOOOO with tagging or removed potential transformer fuses. B OOOOO cO 000 1/27/1998 Positive MAINT IR 98-01 NRC Good communications, coordination, & control was noted dunng a High Pressure 1 234 5 Coolant injection System test. Good self checking techriiques & communications were observed dunng control rod scram time testing. One minor discrepancy was noted involving inadequate documentation of an inservice testing program issue.

A OOOOO OOO cO 000 1/20/1998 MISC MAINT IR 98-01 LICENSEE The licensee initiated action in response to 4 groups of U3 2x2 control rods having 1 234 5 slow 5% insertion scram times. Root cause has not yet been identified, sticking of the scram solenoid pilot valves is suspected. Additional analyses are beinig performed by vendors. (IFl 98-01-03)

AOOOOO "

OOOOO c0 000 1/7/1998 Nega'ive IR 97-12 NRC The brief.ng before a rated flow test was not thorough in that it did not include an 1 234 5 overview of the test & did not address specific actions of personnel involved in the test. The operator initially established a pump fuwrate & due to indicated fluxuations, it was not clear to the inspector that the specified minimum value was A OOOOO met. This was later corrected. B OOOOO cO 000 1/7/1998 Negative IR 97-12 NRC Poor attention to detail during a valve stroke test was identified by the inspector. 1 234 5 The operator did not closely read a procedure step and consequently misunderstood the actions necessary after a valve test stroke time was determined to be outside the normal range.

A OOOOO OOO c0 000 FROM: 10/1/1997 TO: 11/13/1998 Page 4 of 18 FOR PUBLIC RELEASE Last Updated: 7/11/1998

BROWNS FERRY 13-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 1/2/1998 Negative IFl 97-11-01 NRC Two examples of status control issues were identfied by the inspectors during this 1 234 5 inspection. The first example is addressed by the violation for inadeye?* mirol of the CREV system priority selector switch. In addition, the inspectors identfied a drain valve on a non-safety related service air compressor that was not in the A OOOOO required position. Addttional NRC review of recent status controlissues is B OOOOO warrented.

cO OOO 1/2/1998 VIO ENG VIO 97-11-02 NRC Procedural controls of the control room emergency ventiation (CREV) system 1 234 5 priority selector switch were not adequate to ensure that the switch was maintained in the correct position. (NRC found switch in "A* position with train A out of service.)

Further review is necessary regarding testing of the transfer control circuitry.

A OOOOO OOO c0 000 11/'24/1997 Positive IR 97-10 NRC Simulator training for control room operators prior to operational leakage test and 1 234 5 approach to criticality was effective and training goals were met.

A 00000 B B0000 cO 000 11/24/1997 Negatrve IR 97-10 NRC in two instances, Operations personnet did not effectively control important testing 1 234 5 activities. Control of a jumper utilized for High Pressure Coolant injeebon system testing was deficient. Testing which caused actuation of portions of the reactor protection circistry was authorized to be performed during rod withdrawal to A OOOOO criticality. B OOOOO cO 000 10/28/1997 Positive MAINT IR 97-11 SELF Operation actions in response to a Unit 2 single control rod insertion & reactor scram 1 234 5 were good. Procedures were actively referenced & correctly followed. Good performance was noted on the part of the assistant unit operator that identfied an EHC fluid leak during performance of rounds.

A OOOOO O OOO cO 000 10/28/1997 LER MAINT IR 97-11 LER 260/97006 SELF U2 scram during PMT of #1 CV EHC leak repair, operator response, safety system 1 234 5 performance as required. CV cycling caused oscittations in sensed EHC pressure.

Spurious CV fast closure signal resulted in actuation of re8ay in B1 RPS ckt. Relay found to de-energize at voltage higher than other relays. Relay replaced. (SIL 508 A OOOOO related.) B OOOOO cO 000 10/22/1997 Weakness MAINT URI 260/97-10-02 NRC Operations declared individual control rod drives inoperable during routine preventive 1 234 5 maintenance activities & in response to accumulator annunciators during power operations, but in some cases may not have completed a!! actions required by Technical Specificatons. The licensee is evaluating the actual operability status of A OOOOO the accumulators & control rods during these conditions. B OOOOO cO 000 FROM: 10/1/1997 TO: 11/13/1998 Page 5 of 18 FOR PUBLIC RELEASE Last Updated: 7/11/1998

BROWNS FERRY 13-Nov-98 DATE TYPE (s) SEC. SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 10/18/1997 Strength IR 97-10 NRC Operators took prompt & effective actions in response to several significant 1 234 5 equipment problems which necessitated unplanned power reductions.

A 00000 B 00000 c0 000 10/18/1997 Strength IR 97-10 NRC Operations exhibited good overall control of major actwities dunng the Unit 2 1 234 5 refueling cutage exhibited by Operations.

A 00000 B 00000 cO 000 10/4/1997 Positive ENG IR 97-10 LICENSEE 3A recirculation pump MG set control system developed cs,:diations-Ops secured 1 23 4 5 pump, entered single loop ops TS regs met, good precautions to stay clear of instability region. Failed capacitor in stability circuit in MG set voltage regulator. A OOOOO B 00000 cO 000 MAINTENANCE l 7/11/1998 Positive IR 98-04 NRC The licensee effectively performed corrective maintenance on a Unit 3 torus dynamic 1 234 5 restraint that had a leaking oil reservoir. The licensee maintained good control of contractor personnel performing the functional test of the torus dynamic restraint. A OOOOO B 00000 cO 000 7/11/1998 NCV NCV 260/98-04-03 LICENSEE A maintenance worker performed unauthorized work by adjusting valve packing 1 234 5 without operations authorization. Licensee corrective actions were considered good. Additional motor operated valve testing was performed although not required by the as-found condition.

A OOOOO OOO eO 000 7/11/1998 Positive OPS IR 98-04 NRC The prejob briefing for the Reactor Core Isolation Cooling System Rated Flow at 1 234 5 Normal Operating Pressure Test was detailed and instrumentalin successfully coordinating the performance of the various post maintenance tests performed during the surveillance. The operator performing the time-to-rated-flow portion of the A CCCCC test demonstrated a good questioning attitude in questioning the acceptability of an B OOOOO abnormal system valve lineup. Control and supervision of the unit operator trainee was good.

O OOO FROM: 10/1/1997 TO: 11/13/1998 Page 6 of 18 FOR PUBLIC RELEASE Last Updated: 7/11/1998

BROWNS FERRY 13 fdv-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 7/11/1998 Negative IR 98-04 NRC Test equipment was not set up property and contributed to unnecessary 1 234 5 troub;eshooting delays in the calibration of the Reactor Core Isolation Cooling (RCIC) system govemor. Maintenance persennel were unfamiliar with test equipment operation although trained to perform the task. Prehminary heensee A OOOOO investigation efforts were adequately focused on the issues that emerged during B DOOOO perfomance of the RCIC system govemor cahbration.

O OOO 5/5/1998 Posdive IR 98-02 NRC Major maintenance activities on two residual heat removal service water pumps 1 234 5 were conducted well. Placement of the pump assemblies was performed carefully and action to address shaft wear were thorough A OOOOO B 00000 c0 000 5/5/1998 Negative OPS IFl 98-02-05 NRC Overait, conduct of Fix-It-Now team work was well controlled. The inspectors 1 234 5 questioned the procedural guidance and implementation regarding the use of personnel, in some cases, to ensure that a component was maintained in the safe position instead of using a clearance. Licensee management is reviewing the A OOOOO practice to determine if procedural guidance is appropnate and management B DDDDD expect:ations were met. Additional NRC review of the licensee' evaluation is necessary. (IFl 98-02-05) O OOO 5/5/1998 VIO ENG VIO 98-02-03 NRC Additional NRC review identfied that the procedure for testing the SBGT 1 234 5 downstream HEPA filter did not meet the requirements of American National Standard Insttute (ANSI) N510-1975 as required by TS, DOP dispersion testing was not incorporated into the test procedures. (TS 3.7.8.2.a Violation)

A OOOOO e00000 cO 000 5/5/1998 VIO ENG VIO 98-02-02 NRC The licensee did not initially perform an aggressive review of the inspector's concem 1 234 5 that SBGT testing relied upon the +, kill of the maintenance craft to work around procedural obstacles. The NRC s equentfy identified that the model of DOP generator used for testing of the ' dby Gas Treatment (S8GT) and Contol Room A OOOOO Emergency Ventilation (CREV) s! .ns was not equiva' ant to that model required B OOOOO by the procedure. A violation was ,dentifed for failure to follow testing procedures.

O OOO 3'23/1998 Strength IR 98-01 NRC Emergency diesel generator 12 year maintenance preparation, scheduhn9. & 1 23 4 5 execution of work was excellent. EDG inop periods hmited to short periods.

A 00000 s00000 cO 000 3/23/1998 Negative IR 98-01 NRC Some Cause Determination Evaluations are not being performed prompt!y. The 1 234 5 evaluation for Primary Containment integrity System 064A was not promptly updated following the failure of two additional valves. Actions recommended by the Expert Panel were appropriate for other selected issues.

A OOOOO cO 000 FROM.10/1/1997 TO: 11/13/1998 Page 7 of 18 FOR PUBLIC RELEASE Last Updated: 7/11/1998

BROWNS FERRY W3v-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 3723/1998 Positive IR 98-01 NRC Maintenance self-assessment process appeared to be functoning well with some 1 234 5 improvement still needed in proper cause code classification of PERs, identification of PER conditions , and for management to convey expectations to maintenance personnel.

A OOOOO 8 OOOOO cO 000 2/12/1998 Positive ENG IR 97-12 NRC Improvement was noted in the post maintenance testing planning process for 1 234 5 recently completed maintenance work activities.

A 00000 g00000 cO 000 2/12/1998 NCV ENG NCV 97-12-05 11CENSEE A licensee identified & corrected non-cited violation was identified for one example of 1 234 5 an inadequate post-modification test associated with Unit 3 Drywell Leak Detection System Outboard Retum isolation Valve. A OOOOO g00000 cO 000 2/12/1998 Strength tR 97-12 NRC Owra!!, the maintenance department's self assessment program was effective in 1 234 5 that managcnent has identified & pursued areas needing improvement. Numerous maintenance proficiency indicators are rnonitored closely for detection of areas needing improvement. High expectations are established through the establishment A OOOOO of challenging goals. Performance data from completed observation checklists is B OOOOO effectively incorporated into monthly reports. Implementation of the self assessment program was prudently revised by maintenace management to focus on recognized O OOO weak areas. Some of the observation check lists were noted as not sufficiently critical during self assessments. The procedural guidance for the administration of the self assessment checklists does not accurately reflect actualimplementation.

Maintenance management's expectations for feedback to the observed individual, signatures on completed checklists, and degree of self-critism were not being met.

2/12/1998 Positive OPS IR 97-12 NRC Good preparation & detailed planning for the 12 year maintenance inspection on the 1 234 5 3C emergency diesel generator was evident. The training of contract workers using a surplus diesel generator in the training center was a good initiative. Minor issues were identified with the control of contract workers from a security aspect.

A OOOOO B 00000 cO 000 1/22/1998 VIO VIO 97-12-02 NRC A violation of regulatory requirements was identified regarding failure to promptfy 1 234 5 document a condition adverse to quality identified by the NRC. (Worker did not perform EDG filterwork as procedure described.) Previous inspections have identified other examples where the initiation of problem reports was prompted by A OOOOO the NRC. B 000OO cO 000 FROM: 10/1/1997 TO: 11/13/1998 Page 8 of 18 FOR PUBLIC RELEASE Last Updated: 7/11/1998

BROWNS FERRY 13-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 1G11998 MISC OPS IR 97-11 NRC Adequate mechanisms were in place to prompt an annuallicensee review of freeze 1 234 5 protection equipment. Smatt bore & stagnant piping in RHRSW pump rooms could have been given priority during inspection & repair of freeze protection equipment so that the identfied condition of uninsulated small bore piping in colder conditions A OOOOO would not have existed. The licensee's actions to place heaters in & tarpaulins over B DOOOO the RHRSW pump rooms provided a levsl of protection for the uninsulated piping.

O OOO 1G/1998 Positive IR 97-11 NRC Good mechanical maintenance performance was noted during replacement of the 1 234 5 immersion heater coil assembly on the 28 EDG. Effecbve troubleshooting to determine the cause of bumed lugs in the EDG control cabinet identfed probins with the immersion heater even though the heater appeared to be working.

A OOOOO OOOOO cO 000 11G4/1C97 Strength IR 97-10 NRC In- vessel visual inspections were conducted by skillful technicians. Examination 1 234 5 surfaces were clean, examination sensitivity, surface resulution, contrast, and detail was very good. Specific inspection observations indicated that crack like indications on the OD surface of the piping would be identified by the visual examinations A OOOOO observed. B OOOOO cO 000 11/24/1997 Strength IR 97-10 NRC Inservice inspection ultrasonic examination activities were performed & documented 1 234 5 in accordance with applicable approved procedures by knowledgeable and skiilful examiners. A OOOOO B 00000 cO 000 11/24/1997 Positive IR 97-10 NRC The licensee's recent self-assessment on PMT process was very self entical and 1 234 5 provided management with good insight into performance in this area.

A 00000 sD0000 cO 000 11/24/1997 Weakness IR 97-10 NRC The licensee's PMT piarnng process needed improvement & PMT requirements 1 234 5 specified in work orders were not consistent with respect to level of detail. The area or planning of post-maintenance testing was considered a weakness. A OOOOO s00000 cO 000 11/24/1997 Strength IR 97-10 NRC Overall, Unit 2 modification implementation activities were well controlled during the 1 234 5 refueling outage. The licensee effectively planned & scheduled the work activities.

The practice of assigrung Senior Reactor Operators to assist during key testing or work activities was effectve.

A OOOOO OOOOO cO 000 FROM: 10/1/1997 TO: 11/13/1998 Page 9 of 18 FOR PUBLIC RELEASE Last Updated: 7/11/1998

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BROWNS FERRY $3-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 10/19/1997 LER OPS LER 260/97006; PER 97- LICENSEE U2 HPCI steam supply line drain system not working property, large accumulation of 1 234 5 1697 water in line, HPCI declared inoperable. Licensee used boroscope and air testing to investigate for blockage, none found. HPCI retumed to operable status earfy on 10/21' A OOOOO s00000 cO 000 10/18/1997 MISC OPS IR 97-10 LICENSEE U2 tied to grid at 2:18 a.m.10/19/97 to end refueling outage wttich began on 1 234 5 9/27/97. Scheduled for 21 days, completed in less than 22 days. Overall outage planning and scheduling was effective. A OOOOO s00000 cO 900 10/14/1997 Negattve ENG IR 97-10. IR 97-08, IR 97- LICENSEE U3 Div i ECCS Inverter fuse blew. Due to recent modification, power to ATUs was 1 234 5 09 maintained but RCIC inoperable. SCRs found to be degraded. Paper label was stuck on SCR metal bracket which connects to heat sink in cabinet, SCR overheated. Label did not get removed on SCR insta!!ation.

A OOOOO B 00000 cO 000 10/12/1997 NCV IR 97-10; LER SELF Inadvertent engineering safety features actuation occurred during post mod testing 1 234 5 260/97005; NCV97-12-3 of DCN T40231. Pressure Switch Actuation of Main Steam Relief Valves. Worker inadvertentiy allowed the clip on a jumper to contact incorrect relay terminal. Testing could have been done differently to reduce this vulnerability.

AOOOOO OOO cO 000 ENGINEERING 'l 7/11/1998 NCV NCV 260,296/98-04-04 LICENSEE The correction coefficient (TAU) used to adjust the Operating Limit Minimum Critical 1 234 5 Power Ratio (OLMCPR) for slow control rod scram insertion times was incorrect for several Unit 2 and 3 operating cycles. However, the correctect OLMCPR was never exceeded. Weak design controls were in place between the licensee and the A OOOOO contractor performing core reload analysis. The licensee corrective actions were B OOOOO prompt and complete.

cO OOO 6/16/1998 Negatrve NRC ltr dtd 6/6/98 NRC Incomplete and poor quality submittal and nontimely responses to staff's requests 1 234 5 for additional information relating to license amendment request for power uprate.

Quality of submittals and planning for licensing activities needs to be improved. A OOOOO e00000 c0 000 6/16/1998 Negative MAINT IR 98-03 'RC tmplementation of GL 89-10 remained partly incomplete, as the licensee had not 1 234 5 satisfactorily obtained and/or analyzed motor-operated valve (MOV) test data to support r=MO assumptions. A OOOOO B 00000 cO 000 FROM: 10/1/1997 TO: 11/13/1998 Page 10 of 18 FOR PUBLIC RELEASE Last Updated: 7/11/1998

BROWNS FERRY 13-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 6/16/1998 NCV NCV 98-03-06 LICENSEE The licensee identified that testing of a control room emergency ventilation system 1 234 5 damper did not fully implement Technical Specification (TS) requirements. The problem was idenbfied dunng reviews for Generic Letter 96-01, Testing of Safety-Related Logic Circuits.

A OOOOO OOOOO c0 000 6/16/1998 URI URI 98-03-02 LICENSEE Testing of the Standby Gas Treatment relative humidity heater flow switches was 1 234 5 well controlled and conducted in accordance with procedures. Second party checking and communication practices were good. Some inconsistencies were noted it'volving the testing methodology and measurement of air flowrates. An A OOOOO appa:ent discrepancy between TS requirements and the test procedure was B OOOOO identified by the licensee. An unresolved item tvas opened to address additional review.

O OOO 5/5/1998 Positive IR 98-02 NRC The inspector concluded that the licensee's Qualified 50.59 Preparer Training met 1 234 5 ANSI-3.1-1981. Six 10 CFR 50.59 safety evaluations chosen for review, five were determined to be technically adequate. One safety evaluation contained a minor d***" Y A OOOOO aO00OO cO 000 5/5/1998 VIO MAINT VIO 98-02-04 NRC Periodic replacement of the High Pressure Coolant injection System turbine exhaust 1 234 5 rupture disc assembly was performed satisfactorily except that the as-found inspection process was not adequate to identify that the disc material was degraded. The licensee did not identify the degradation unbl the inspectors A OOOOO questioned the inspection. (Critenon XVI Violation) B OOOOO cO 000 3/23/1998 URI URI 98-01-01 NRC During review of offgas system radiabon monitoring instrumentation calibration & 1 234 5 setpoints, an unresolved item was ident:fied. It was not clear how the licensee encorporated changes in the monitoring instrumentation efficiency factors. Additional NRC inspection of issues including control room annunciator setpoints & procedures A OOOOO is needed. B OOOOO cO 000 3/23/1998 Positive IR 93-01 NRC The Operating Experience Program was effective in reviewing industry issues & 1 234 5 assigning and tracking action items. 'ssues were adequately reviewed for technical merit & resolved in a timely manner. A OOOOO B 00000 cO 000 3/23/1998 Negative IR 98-01 NRC Engineering self-assessments performed in accordance with TI-356 are useful in 1 234 5 identifying some deficiencies; however, do not eva!uate performance in several key areas & processes. A OOOOO s00000 cO 000 FROM 10/1/1997 TO: 11/13/1998 Page 11 of 18 FOR PUBLIC RELEASE Last Updated: 7/11/1998

BROWNS FERRY 13-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 2/12/1998 NCV NCV 97-12-03 LICENSEE A ticensee identified & corrected non-cited violation was identified involving different 1 234 5 residual heat removal service water pump operability requirements in Technical Specifications and the Updated Final Safety Analysis Report. The licensee's safety assessment provided in the Licensee Event Report was thorough.

A OOOOO OOO cO 000 1/2/1998 Negative MAINT URI 97-11-03 NRC Portion of CREV system irutiation logic relating to startup of " backup" train not 1 234 5 tested. (One side tested by a PCIS test.) Feature must operate to get second train start if first train fails. Review in progress, inadequate review of CREV mod may have been cause.

A OOOOO 8 OOOOO cO 000 112/1998 DEV OPS DEV 97-11-04 NRC Inspectors identified that the licensee failed to revise procedures to declare the 1 234 5 applicable system or train inoperable when certain motor-operated valves were placed in their non-safety posdons. A OOOOO s00000 c0 000 1/2/1998 NCV MAINT NCV 97-11-05 UCENSEE The licensee failed to evaluate test data to assess its Generic Letter 89-10 program 1 234 5 design assumptions & improperty used actuator stall efficiency in evaluating motor-operated valve operability. A OOOOO a00000 cO 000 1/2/1998 VIO MAINT VIO 97-11-06 NRC Inspectors identified that the licensee failed to prepare motor-operated valve trend 1 234 5 reports in accordance with procedure requirements.

A 00000 g00000 c0 000 1/2/1998 Negative PLT SUP 1R 97-11 NRC On two occasions during the inspection period, the NRC prompted problem 1 234 5 evaluation reports (PERs) to be written. The first example was an NRC identified deficiency with a main steam pressure instrument calibration calculation. The original set point & scaling calculation for the main steam pressure instruments A OOOOO analyzed for a calibration frequency of 12 months versus the surveillance instruction B OOOOO frequency of 18 months. The second example involved problems with radiation monitor RM-90-130. In both of these examples, personnel did not initiate PERs O O 'O O when they were warranted.

1/2/1998 Negative IR 97-11 NRC Review of the technical operability evaluation (TOE) to evaluate the main steam line 1 234 5 pressure transmitters, which were installed in the plant with incorrect upper range pressure limits, identified deficiencies with the TOE. The overall results of the TOE were not affected. No regulatory violations were identified conceming these non-A OOOOO safety related transmitters. B OOOOO cO 000 FROM: 10/1/1997 TO: 11/13/1998 Page 12 of 18 FOR PUBLIC RELEASE Last updated: 7/11/1998

BROWNS FERRY 13Mn-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 1/2/1998 Positive IR 97-10 NRC The licensee's incident investigation team performed well in investigating the 1 234 5 equipment issues which caused the Unit 2 scram. The team studies available information, developed a theory of the cause, and in a prompt manner performed electncal testing which supported the postualted cause. The investigation into the A OOOOO EHC fluid leaks was also thorough & determined the cause of the leaks in a B OOOOO reasonable time period.

O OOO 1/2/1998 Weakness MAINT IR 97-11 LICENSEE Although the licensee's actions to decrease the oil particulate levels in the RCIC 1 23 4 5 systems were adequate, the RCIC oil particulate levelissue represents another example of the difficulties that the licensee is experiencing with the tube oil analysis program.

A OOOOO OOO c0 000 11/24/1997 Negative IR 97-10 NRC The inspectors identified that the surveillance procedure for inspection of the drywell 1 234 5 was not sufficiently detailed to ensure that the liner sealant conditions were properly assessed & documented. Subsequent inspection was detailed & the conditions were fund to be acceptable. The licensee's actions to excavate & replace portions of A OOOOO the drywell liner seal were appropriate. B OOOOO cO 000 11/24/1997 Strength IR 97-10 NRC Based on the inspectors review of Power Range Nuclear Monitoring (PRNM) design 1 23 4 5 changes involving the system installation for Browns Ferry Unit 2, the licensee's installation, testing, maintenance, and training were acceptable. Group B design changes involved revising the average power range monitor / rod block monitor A OOOOO setpoints and these design changes were suported by new PRNM setpoint B OOOOO calculations based on the proposed hardware configuration and on analytical limits for maximum extended load line limit operation. These setpoint changes were also O OOO considered acceptable.

11/24/1997 Negative IR 97-10 NRC The licensee implemented a modification to reduce me chances of a spurious Main 1 234 5 Steam isolation Valve Closure on a scram. Detailed testing & calculations were performed to determine the proper capacitance value to be installed. The inspectors identified a deficiency in that the calculation utilized a nominalinstrument setpoint A CCCCC instead of the maximum permissible as found value. Although the calculated B OOOOO response time was slightly lower than it would have been with the proper setpint applied, regulatory requirements were not exceeded & the calculation was O O O O' subsequentty revised.

11/24/1997 Licensing IR 97-10 NRC Two examples were noted in which Ucensee Event Reports did not provide good 1 23 4 5 assessments of safety consequences. The licensee's report on an inoperable inboard containment isolation valve did not address a single failure of the outboard containment isolation valve. The initial report addressing a design deficiency A OOOOO involving simultaneous purging or inerting of the drywell & supression chamber while B OOOOO at power did not include a thorough safety assessment of the issue.

O OOO FROM: 10/1/1997 TO: 11/13/1998 Page 13 of 18 FOR PUBLIC RELEASE Last Updated: 7/11/1998

BROWNS FERRY 13-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 1W14/1997 Negative OPS IR 97-10 NRC Following identification of an adverse condition on the Unit 2 High Pressure Coolant 1 234 5 injection system oil filters, actions regarding the conditions of the Unit 3 HPCI oil filters were not prompL Licensee management had clearty indicated that safe operation of Unit 3 was the highest prionty during the Unit 2 refueling utage.

A OOOOO Information indicated that in this instance, some licensee personnel did not property B OOOOO carry out management expectations.

O OOO PLANT SUPPORT ' l 7/11/1998 Positive IR 98-04 NRC Facility radiological conditions in radioactive waste storage areas, health physics 1 234 5 facilities, and Turbine and Reactor Buildings were found to be appropriate and the areas were property posted and material appropriately labeled. Personnel dosimetry devices were appropriately worn. Radiation work activites were appropriately A OOOOO planned. Radiation worker doses were being maintained well below regulatory limits B OOOOO and the licensee was maintaining exposures ALARA. A special team was planning an aggressive U3 drywell cleanup. The Whole Body counting program was O OOO performed as procedurally required.

6/16/1998 Posrtive IR 98-03 NRC The inspector determined that the licensee had procedurally established a process 1 234 5 to ensure that personnel who were granted unescorted access were trustworthy, reliable, and do not constitute an unreasonable risk to the health and safety of the public.

A OOOOO OOOOO cO 000 6/16/1998 NCV NCV 98-03-07 LICENSEE A non-cited violation for failure to meet NRC requirements in 10 CFR 50 Appendix B 1 234 5 Criterion lit Design Control was identified. Discussion with cognizant licensee personnel and a review of performance records determined the percentage unavailability of the Radeon continuous air monitors was an area that could be A OOOOO improved. The licensee was conducting thorough formal RP and chemistry audits B OOOOO as required by Technical Specifications and conducting self-assessments. The licensee was developing corrective action plans, trending, and completing corrective C0 D.O O actons in a timely manner.

6/16/1998 Positive IR 98-03 NRC The water chemistry control program met the regulatory requirements and the 1 234 5 licensee was using depleted zinc oxide tc help lower general and component radiation dose levele,.

A OOOOO B 00000 cO 000 6/16/1998 Positive IR 98-03 NRC Radioactive material was labeled appropriately, and areas were property posted. 1 234 5 Personnel dosimetry devices were appropriately worn. Radiation work activities were appropriately planned. Radstion worker doses were being maintained well below regulatory limits. Contamination control, although challenging was effective.

A OOOOO Reduction in the generation of radwaste demonstrated agressive management. B OOOOO cO 000 FROM.10/1/1997 TO: 11/13/1998 Page 14 of 18 FOR PUBLIC RELEASE Last Updated: 7/11/1998

BROWNS FERRY 13-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 3G3/1998 Positive IR 98-01 NRC During troubleshooting & repairs to an electrohydraulic system pressure switch, the 1 234 5 ficensee used mockup training as an effective ALARA technique. The prejob brief was comprehensive & clearly defined the scope of the work. Good teamwork was noted between the working groups.

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cO 000 323/1998 Positive IR 98-01 NRC Fire barrier penetration seal surveillance procedures were adequate & were being 1 234 5 effectively implemented with surveillance inspections being performed more frequently than required. A OOOOO s00000 c0 000 2/12/1998 MISC IR 97-12 NRC Liquid effluent releases reviewed dunng this inspection were found to meet the 1 234 5 regulatory requirements & the compensatory anatysis permitted by the Offsite Dose Calculation Manual during the effluent !adiation monitor O-RM-130 outage were satisfactory.

A OOOOO OOO cO 000 2/12/1998 Positive IR 97-12 NRC Radeon problem reports were aggressively evaluated, cause analysis performed & 1 234 5 corrective measures to prevent recurrence instituted.

A 00000 s00000 cO 000 2/12/1998 Positive IR 97-12 NRC The licensee had effectively implemented a program for shipping radioactive 1 234 5 materials required by NRC and DOT regulations. Radiological conditions in radioactive waste storage areas were observed to be good Material was labeled appropriately, and areas were property posted.

A OOOOO OOOOO c0 000 2/12/1998 Negative OPS IR 97-12 NRC The NRC & licensee goal for declaration of an emergency classification within 15 1 234 5 min. of event recognition was exceeded by 12 min. during the loss of station power event on March 5,1997. It was not clear to the incpector that the licensee's evaluation of this aspect was self-critical and that the delay was sufficientty A OOOOO explained. B BOOOO cO 000 2/12/1998 Strength IR 97-12 NRC The Emergency Preparedness program overall continued to be strong. Emergency 1 234 5 Response facilities were satisfactority maintained. Emergency Preparedness audits were organized & objective & satsifed requirements of 10 CFR 50.547. A OOOOO B 00000 cO 000 FROM: 10/1/1997 TO: 11/13/1998 Page 15 of 18 FOR PUBLIC RELEASE Last updated: 7/11/1998

BROWNS FERRY 13-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 3/4/1998 Strength IR 98-01 NRC Licensee <onducted audits were thorough, complete, and effective in terms of 1 234 5 uncovering weaknesses in the security system, procedures, & pracbces. Audit findings & recommendatons were reviewed, appropriately assigned, analyzed, &

prioritized for corrective action. The corrective actions taken were technicalty A OOOOO adequate & performed in a timely manner. B OOOOO cO 000 2/4/1998 Positive IR 98-01 NRC Planning & other efforts successful in transition to contract security force. 1 234 5 Contractor Protective Services security personnel met the suitability requirements for employment & were appropriately trained in accordance with the regulatory requirements specified in the Physical Security Plan, Contingency Plan, Training &

A OOOOO Qualification Plan, & associated security program implementng procedures prior to B OOOOO 1 heir assignment.

O OOO 1/2/1998 Negative SAOV IR 97-11 NRC Unexpected indications on the radioactive effluent monitor recorder were not 1 234 5 thoroughly investigated prior to discontinuation of compensatory act:ons required for an inoperable monitor. The licensee subsequently completed a detailed investigation which identified that a leaking valve had caused the unexpected A OOOOO indications. The investigation also concluded that the monitor was not inoperable & B OOOOO that regulatory requirements were met dunng the period.

O OOO 11/24/1997 Positive IR 97-10 NRC The inspectors determined the licensee was effectively conducting formal RP audits 1 234 5 as required by Technical Specifications and conducting self-assessments. The licensee was effectively developing corrective action plans & completing corrective actions in a timely manner.

A OOOOO OOOOO c0 000 11/24/1997 Strength IR 97-10 NRC Radiation work actiwties were planned, radiation worker doses were being 1 234 5 maintained well below regulatory limits & the licensee was continuing to maintain exposures as low as reasonably achievable. A OOOOO sD0000 cO 000 11/24/1997 Positive IR 97-10 NRC Radiological facility conditions & housekeeping in radioactive waste storage areas, 1 234 5 health physics facilities, auxiliary building & refueling floor were observed to be good, material was labeled appropriately, & areas were property posted- A OOOOO e00000 c3 000 11/24/1997 Strength IR 97-10 NRC The licensee's Nuclear Assurance & Licensing assessments of the facilitity's fire 1 23 4 5 protection program were comprehensive & effective in identifying fire protection program performance to management. A OOOOO s00000 c0 000 FROM: 10/1/1997 TO: 11/13/1998 Page 16 of 18 FOR PUBLIC RELEASE Last Updated: 7/11/1998

BROWNS FERRY 13-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 11/24/1997 Positive IR 97-10 NRC The fire brigade organization & training met the requirements of the site procedures 1 234 5 and the performance by fire brigade as documented by drill evaluations was good.

A 00000 B 00000 cO 000 11/24/1997 Strength IR 97-10 NRC The fire protection program implementing procedures were well written & met the 1 234 5 licensee's commitments to the NRC. Implementation of the fire protection &

prevention procedures & the general housekeeping for control of compbustibles within the plant were satisfactory. Tt:e prefire plans reviewed by the inspector were A OOOOO found to be satisfactory, however, had not been updated since 1992 to reflect Unit 3 B OOOOO restart.

O OOO 11/24/1997 Strength IR 97-10 NRC The maintea.ance & material condition of the fire protection equipment was good. 1 234 5 No fire watch compensatory measures were required for the fire protection features which had opened work orders or were out of service. Long term plans to resolve fire protection system water leakage were in place.

A OOOOO OOOOO cO 000 11/24/1997 Strength IR 97-10 NRC There was not a high backlog of open work orders for fire protection features. The 1 234 5 number of npen Problem Evaluation Report issues associated with the fire protection program or components was small. Corrective maintenance on degraded fire protection systems was being property scheduled.

A OOOOO OOOOO cO 000 10/2/1997 Negative UCENSEE Bamwell notified the licensee that a hic shipped from DFNP (containing spent resin 1 234 5 from condensate demins) was found to contain an explosive gas mixture. Initial reports indicate that the gas in question is methane. Unknown, licensee testing found low levels of localized microbic infestation, bacteria believed not sufficient to A OOOOO cause gas quality reported. B OOOOO c0 000 FROM: 10/1/1997 TO: 11/13/1998 Page 17of 18 FOR PUDLIC RELEASE Last Updated: 7/11/1998

BROWNS FERRY 13-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES SMM Template Codes: SALP Functional Areas: ID Code:

~ ~

. 1A ~ ' OPERATION PERFORMdNCE - NormEOperations 'l I  ! LICENSEE ~LiC

'ENSEE~

1B . OPERATION PERFORMANCE Operations During Transients ENG , ENGINEERING NRC .NRC 1C . OPERATION PERFORMANCE - Programs and Processes MAINT MAINTENANCE SELF SELF-REVEALED 2A MATERIAL CONDITION - Equipment Condition OPS . OPERATIONS 2B MATriRIAL CONDITION - Programs and Processes PLT SU PLANT SUPPORT 3A HUMAN PERFORMANCE - Work Performance SAQV- ' SAFETY ASSESSMENT & OV 3B HUMAN PERFORMANCE - KSA 3C HUMAN PERFCr4MANCE- Work Environment 4A . ENGINEERING / DESIGN - Design 4B . ENGINEERING / DESIGN - Engineering Support 4C . ENGINEERING / DESIGN - Programs and Processes SA . PROBLEM IDENTIFICATION & SOLUTION - Identification lSB , PROBLEM IDENTIFICATION & SOLUTION - Analysis j5C PROBLEM IDENTIFICATION & SOLUTION - Resolution Eels are apparent violations of NRC requirements that are being considered for escr.;ated 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 informati >n 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 reached its final conclusiores on the issues, and the PIM entries may be modified when the final conclusions are made.

FROM: 10/1/1997 TO: 11/13/1998 Page 18 of 18 FOR PUBLIC RELEASE Last Updated: 7/11/1998

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