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Suppls 870203 Response to GG Zech Re Engineering Change Notice Closeout Effort & FSAR Discrepancy Described in SQ-CAR-86-04-21,per F Mccoy & M Branch Requests During 870410 Meeting.Addl Info & List of Commitments Encl
	ML20214N926
Person / Time
Site:	Sequoyah
Issue date:	05/22/1987
From:	Domer J; TENNESSEE VALLEY AUTHORITY
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	NUDOCS 8706030144
	Download: ML20214N926 (15)
	v • d • e

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         .e TENNESSEE VALLEY AUTHORITY :
                                                                   ' CH ATTANOOGA. TENNESSEE 37401 SN 157B Lookout Place MAY 221987 U.S. Nuclear Regulatory Comission ATTN: Document Control Desk i                       Washington, D.C. 20555 Gentlemen:

In the Matter of ) Docket Mos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) UNITS 1 AND.2 - ENGINEERING CHANGE NOTICE (ECN) CLOSEOUT AND FSAR UPDATES - SUPPLEMENTAL RESPONSE e This supplemental response to Gary G. Zech's letter to S. A. White dated

                      -December 18, 1986, regarding the ECN closure effort and_the FSAR discrepancy described in SQ-CAR-86-04-21, is provided in accordance with'a                                        l request from Frank McCoy and Morris Branch during an April. 10, 1987 meeting at SQN. The initial response to Mr. Zech's December 18, 1986 letter was provided in a letter to J. Nelson Grace from J. A. Domer dated                                         i February 3, 1987.                     Enclosure 1 of this supplemental response provides.                          '

additional information about the ECN closure effort and enclosure 2 provides additional information about the FSAR corrective actions. Enclosure 3 contains the list of comitments in enclosures 1 and 2.

) If you have any questions, please call M. R. Harding at (615) 870-6422. 1 To the best of my knowledge, I declare the statements contained herein are complete and true. + i 1 Very truly yours, TENNESSEE VALLEY AUTHORITY

                                                                                                . d.
                                                                                           )J.A.Domer,AssistantDirector Nuclear Safety and Licensing Enclosures cc: See page 2 i
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i 4 8706030144 870522 7-PDR ADOCK 0500 P An Equal Opportunity Employer

U.S. Nuclear _ Regulatory Conunission f hj h[ cc (Enclosures): Mr. G. G. Zech, Assistant Director for Inspection Programs Office of Special Projects Division of TVA Projects ! U.S. Nuclear Regulatory Commission 1 Region II 101 Marietta Street, NW, Suite 2900-Atlanta, Georgia 30323 Mr. J. A. Zwolinski, Assistant Director . for Projects Division of TVA Projects Office of Special Projects i U.S. Nuclear Regulatory Commission 4350 East West Highway . EWW 322 J Bethesda, Maryland 20814. l Sequoyah Resident Inspector i Sequoyah Nuclear Plant i 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 1 .I

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E

                                                                            . ENCLOSURE 1

. SUPPLEMENTAL INFORMATION REGARDING THE ECN CLOSURE EFFORT This enclosure provides details about the type and complexity of ECNs -

which have been closed by the ECM closure effort, compensatory measures taken which address the minor discrepancies identified during the closure -

i

effort, and the manpower allocations required to support closure of the

_i ECW backlog at SQN by October 1988 as committed in TVA's original response.

As described in TVA's original response, the ECN closure group has closed ! approximately 100 ECNs (selected at random) from the ECN backlog at SQN. j Attachment 1 provides a breakdown of the 104 ECNs closed by this effort. i From the table in attachment 1, it can be seen that this effort affected a cross section of the modification disciplines (principally mechanical and i electrical). Of the 104 ECNs closed, 43 were mechanical (M), 44 were electrical (E), 10 were civil (C), and seven were mixed disciplines.. These ECNs ranged in complexity from affecting one system and no drawings ! I , to involving three systems and 42 drawings. An average of four to five I drawings and one to three workplans per ECN were closed in this effort, i l Attachment 2 provides a key to the system numbers used in attachment 1. f As explained in TVA's original response, the types of errors identified by the ECN closure process have been minor in nature. The one area of 4 discrepancy that does appear more often, however, is with the 47W611 } series logic diagrams. This drawing series, because of the number of 4 discrepancies identified, has been removed from the main control room (MCR). The operations personnel instead rely on other MCR drawings (e.g., 1 flow, control, and single-line diagrams). TVA's current plans involve

including seven of the principle logic diagrams in the "as constructed"
drawing program to be verified and corrected before unit 2 restart in I accordance with SQN's previous commitments (letter from R. Gridley to J. Nelson Grace dated December 12, 1986).

i ! The schedule for closure of the ECM backlog at SQN as provided in TVA's original response is to close the approximately 1,200 ECNs by October 15, 1988. Approximately 670 of those are on Critical Structures, Systems, and Components (CSSC). This schedule is based on six full-time .

individuals working in the closure group and approximately 19 man-hours l

, required to review each ECN for closure. Although not a commitment, SQN's l schedule for completion of the 670 CSSC ECNs is December 1987, with the

balance of the backlog resolved by October 15, 1988 (as previously j committed). This schedule supports inclusion in the 1989 FSAR update and
completion of the FSAR corrective actions described in SQN's original response.

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   , _      -          .~.  .___.-____ ~__                       _ _ _ - - . _. . _ _ _ __. . ._ - - - - -

i l ENCLOSURE 2 SUPPLEMENTAL INFORMATION REGARDING FSAR CORRECTIVE ACTIONS TVA's original response provided the corrective actions planned to resolve i the FSAR discrepancies. This supplemental response describes SQN's efforts to compensate for the FSAR discrepancies when internal TVA - reviews / evaluations and NRC review / evaluations involving the FSAR are conducted. Additionally, this response describes how discrepancies identified during the FSAR verification program will be handled. l On January 28, 1987, the Site Licensing Staff issued a memorandum from-l M. R. Harding to L. M. Nobles (Acting Plant Manager) and D. W. Wilson, + Division of Nuclear Engineering.(DNE), concerning 10 CFR 50.59 evaluations. This memorandum stated that, in preparation of Unreviewed Safety Question Determinations (USQD), evaluators are not to rely solely i on the FSAR. . SQN's technical specifications, verified "as-constructed" drawings, verified design criteria, and.other resources should be utilized in addition to the FSAR for USQD evaluations. SQN Standard Practice (SQA)-119. "Unreviewed Safety Question Determination," has been revised to incorporate this polict. Likewise, DNE SQN Project is issuing a memorandum to ensure that the FSAR is not the sole source of information 4 in preparation of USQDs and modification packages and will issue Nuclear Engineering Procedure (NEP)-6.6, " Safety Evaluations," by June 30, 1987, to include this policy. Because of the deficiencies with the SQN FSAR, TVA will provide a copy of . critical "as-constructed" drawings to NRC Washington and Region II Incident Response Centers by June 30, 1987. These drawings will include flow, logic, control, and single-line drawings for those systems esstatial to safely operate the plant and are currently included in the FSAR. TVA's plans for periodically updating the drawings provided to NRC's incident response centers will be included in the June 30, 1987 drawing submittal referenced above. This will provide NRC with up-to-date information to assist in responding to and analyzing emergency situations that may-i arise. Furthermore, TVA will provide specific information, in~each I application, as necessary to support technical specification changes by ! supplementing the FSAR where deficiencies exist. ! The FSAR Verification Program (described in TVA's initial response) will l use the established corrective action program (Administrative Instruction j [AI]-19, Part 1, " Conditions Adverse to Quality") to currect design j discrepancies identified during the verification process. This approach

will ensure that Conditions Adverse To Quality (CAQs) are promptly l identified, documented, evaluated, corrected, and reported to management l in a manner consistent with their importance to safety.

i 1

ENCLOSURE S LIST OF COMMITMENTS

1. By June 30, 1987, DNE will issue NEP-6.6 to include the policy for not solely relying on the SQN FSAR for 10 CFR 50.59 evaluations.

2. By June 30, 1987, provide NRC copies of the critical "as-constructed" drawings for SQN restart'and TVA's plans for periodically updating those drawings. These drawings will include flow, logic, control and-single-line drawings for those systems essential to operate the plant and are currently included in the FSAR.

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Attachmsnt 2 y ' Standard Practice Page 66 T SQM2 . Revision 23 f ATTACHMENT.C < SYSTEM CODES 1 Main Steam System inc1'uding Steam Generator Blowdown 2 Condensate System ..t

                                                                                                                                            ._ _. l . c 3     Main,and Aux 111ary Feedwater System                                                     ~

I' . 5 Extraction Steam System - {

                                                                                                                                                          ,I.?, :

6 Heater Drains and Vents System ~.I; . f 7 TurbineExtractionTrapsandDra[nsSystem _ f ,, -{:: - 8 Miscellaneous Turbine Connections ,

                                                                                                                                         . . .. _..[.f.z, 9     Misc 511aneousTurbinehentSystems                                                                         -
                                                                         ~                                                                                    ..

4 - 12 Aux 111ary Boller Systems 13

     ,.-                           Fire Protection i0ther than HPFP and-C02 fire protection) Systems
                                ~
       .                     14   Condensate emineralizer System '
               ~

15 Steam Generator Blowdown System I 18 Fuel 011 System ,, 19 Lig5 ting - Off 011 and Air Piping System 20 Central Lubricating 011 System 24 Raw Cooling Hater System 25 Raw Service Hater System' 26 High-Pressure Fire-Protection System . 27 Condenser Circulating Hater System 28 Hater Treatment System 29 Potable Water Olstribution System L t 30 Ventilation System 0323S/ jaw w e

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Attachment 2. '

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Standard Practice Page 67 . SQM2 . Revision 23 ATTACHMENT C (Continued) SYSTEM CODES - Heating and Air Conditioning System 31 32 Control Air System .

                                           ~
,           .                        33    S'ervice Air System                                                                   "
             .                       34    Vacuum Priming System                                         -

35 Generator Cooling System ..

                                                                                                     ' ;   ~

36 Feedwater Secondary Treatment System -

                                                                                             ~
                                                                                          ~~ ' ~ ~

37 G1,and Seal Water System ~ ~ - - - ~ ~ ~ 38 Insulating 011 System ' 39 CO, Storage,. Fire Protection, and Purging System 40 .StitionDrainageSystem 41 Layup Ha'ter Treatment System' 42 Chemical Cleaning System 43 Sampling and Water Control System.

44 Bullding Heating System (Instruments and Controls) 46 Feedwater Control System , 47 Turbogenerator Control System 49 Breathing Air System l l - 50 Hypochlorits System 51 Raw Water Chlorination (Acrolein) System -

52 System Test Facility (Instrumentation) 54 Injection Water System ; 1 0323S/dri n e o

   ~ ._       .'

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         ',                                             Attachment 2 ,

Standard Practice ^ Page 68 t~ SQM2 .' ' Revision 23 ATTACHMENT C (Continued) , SYSTEM CODES 55 Annunciator and Sequential Events Recording System f 56 Tempe,rature Monitoring System

          ,                    57    Genfrator Associated Electrical System (Including
                    ..               Protection, Excitation, and Voltage Regulation)                      -

58 Main Generator Bus Cooling System 4 ., f 59 Demineralized Water'and Cask Decontamination

                                                                                                                                                                 'e 61    Ice Condenser System                                                            -

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                                                                                            .-n-

1. 62 Chemical and Volume Control System ,. , , ,

63 Safety Injection Systeiri 64 Ice Condenser Containment System . 65 Emergency Gas Treatment System 67 Essential Raw Cooling Water (ERCH) System 68 Reactor Coolant System 70 Component Cooling System

       .                      72     Containment Spray System 74     Residual Heat Removal System 77     Waste Disposal System 78     Spent-Fuel-Pit Cooling System (Fuel Holding and Cranes)                                                                         l s

79 Fuel Handling Tools and Fixtures 80 Primary Containment Cooling System 81 Primary Makeup Hater System

 .                 0323S/ jaw             ,

            ,                                                  Attachment 2 ,
                                                                        <. '*s M

Standard Practice Page 69 p ,,. SQM2 .', Revision 23 ATTACHMENT C , , (Continued) .

SYSTEM CODES _.

82 Standby Diesel Generator System '" ) f 83 Hy,drogen Recombination System 2,, 84 ,ffood Mode Boration System- . [ .. . - ~, f { 85 Control Rod Drive System . t , 86 Diesel Starting Air System #Y, a t: 87 Upper Head Injection System - -

                                                                                     ~                        ~'

88 -Containment Isolation System - - 7. ' 'i ~ Ci= z

l 90 Radiation Monitoring System - f 92 94 Neutron'Monttoring System { ,, _ Incore Flux Detectors

                                          ~
        ,                             99        Reactor Protection System

114 Plant Equipment - General Support and Minor Maintenance-4

![i Performed in Response to SI-114.1 and SI-114.2 150     _ Measuring and . Test Equipment 4      ,

162 Plant Equipment - General Support and Minor Maintenance i Performed in Response to SI-162.1 and 51-162.2 l 200 Status Monitor System . ! 201 480-V Electrical Boards and MCC ) 202 6900-V Electrical Boards (and Logic Panels) ! 234 Heat Tracing System . 241 Stic' yard n and Transformers 244 Communications Systems 245 Security Systems

. 0323S/ jaw l

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               ,                                                                                             Attachment 2 F                                                                                                                     ,                                                                                                        i i:                                                                                                 Standard Practice                               Page 70                                                           .

SQM2 . Revision 23 ATTACHMENT C (Continued) SYSTEM CODES 247 Lighting Systems I 4 f 250 250,V DC,125-V, DC,120-V AC, Low Voltage Power . 255 Dat[LoggerandAcquisitionSystem [. ., ... L 260 Chemical Lab Test Equipment -

i [ 263 Condenser Tube Cleaning System - a [ ; , 264 Technical Support System ' - [ 265 Health Physics Test Lab Equipment ' -7 ' "

                                                                                                                                                                                                                                  "A " '" '-

1. . c. , . .

266 Mechanical Test Equipment 268 Permanent Hydrogen Mitigation System

        ,                                             282-       Fleid Services Facility Electrical System l                                                      283        Low Level Rad Waste Facility ' '                                                                                                                                            '

r 301 Computer Systems

.      1 302        Penetrations i

_. s T1 303 Cranes 305 Sewage f 306 Hiscellaneous Office Equipment 307 Elevators - 309 Recirculation Flow Control l 311(31A) Control Building HVAC

312(318) Yard and Miscellaneous Mechanical Unit Equipment

;                                                    313(31C) Aux 111ary Building HVAC (Instrument and Valves) i, i

0323S/dr1 4 4

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

              .   ,                                                                                                                                          l V.            ,
                .                                                 Attachment 2.,
          "                                                                 6                                              '

Standard Pract' ice ' Page 71

          '-                                                                                          SQM2               '

Revision 23 1 ' ATTACHMENT C (Continued) SYSTEM CODES . 317 Miscellaneous and Power Outlets - 320 Holsts and Platforms 350 IWstrument Hangers l . 352 Instrument Conduit Hangers t . 361 Cables ~ - 362 Cable Trays .

i 363 Condutt ,

                                                                                                                ,-     ~.'         -- " 1.                2.

Rolling Doors

410 ,, f 500 Instrument Panels, Control Room, and Status Monitor Boards - 928 ,' Makeup Hater Treatment Plant 959 Demineralized Water Storage and Dis 991

Junction Boxes Some records exist with junction boxes identified as system 360.

u J I 1 a 0323S/ jaw I L. .

   .-.                           - _ _                :   __             -.    . _ -      - - - . - .                     ..}}

ML20214N926

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