ML19347E518

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Submits Seismic Design Margin Review Program Plan & List of Components to Be Investigated,Required by Item 2.C(6) of Full Power Ol.Program Expected to Be Completed & Results Available by 820102
ML19347E518
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 05/05/1981
From: Mills L
TENNESSEE VALLEY AUTHORITY
To: Schwencer A
Office of Nuclear Reactor Regulation
References
NUDOCS 8105120313
Download: ML19347E518 (12)
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e TENNESSEE VALLEY AUTHORITY CH ATT ANOOGA. TENNESSEE 374ot 400 Chestnut Street Tower II e ")/ / , $p  %

May 5, 1981 S N

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Director of Nuclear Reactor Regulation va, % , % , '

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Attention: Mr. A. Schwencer, Chief Licensing Branch No. 2 / P Division of Licensing U.S. Nuclear Regulatory Commission

<v gN Washington, DC 20555

Dear Mr. Schwencer:

In the Matter of ) Docket No. 50-327 Tennessee Valley Authority )

In the TVA/NRC meeting of April 1, 1981, NRC requested that TVA submit a seismic margin program plan and a list of components to be investigated.

Enclosed is TVA's program plan for the seismic design margin review of the Sequoyah Nuclear Plant as required by item 2.C(6) of the full power operating license for unit 1.

In September 1981, TVA will get in touch with NRC to discuss the advis-ability of a TVA/NRC meeting concerning interim progress. The TVA program '

is expected to be completed and results available for presentation by January 2, 1982.

Very truly yours, TENNESSEE VALLEY AUTHORITY f

M. Mills, Manager Nuclear Regulation and Safety Sworn tgand subscribed before me thisd- day ofh444 1981 0

  • Notary Public My Commission Expires '5"/$

Enclosure OD I s

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. . ENCLOSURE

. SEISMIC DESIGN MARGIN REVIEW PROGRAM _

SEQUOYAH NUCLEAR PLANT .' a.,

Introduction The TVA seismic evaluation program was presented to the Nuclear Regulatory Commission (NRC) in March 1979. Because of time limitations, NRC was not able to complete its review of all equipment; only mechanical equipment critical to safe shutdown was reviewed and documented. The werk completed and the scope of work to be done are discussed for each of the four items of seismic qualification. Items 1 and 2 were completed in 1979, and no further work is anticipated en these items. The TVA program concentrates on item 4, safety-related equipment.

The format of the March 1979 presentation was extremely effective in communicating basic technical information for both NRC and TVA. This presentation consisted of the exchange of technical data, criteria, and engineering rationale directly across the table between TVA and NRC cognizant engineering employees. Copies of technical information such as pertinent criteria, qualification report excerpts, engineering notes, etc.,

were provided to the NRC representative upon request as the presentation proceeded.

TVA proposes that this same informal technical information exchange format be used for a followup presentation. For obvious reasons, the presenta-tion would be most effective if conducted in the TVA offices in Knoxville.

TVA Program

1. Category I structures - Category I structures have been shown ~

acceptable for seismic loading associated with the 84th perce.ntile site-specific response spectra. This includes the original analyses of Sequoyah Nuclear Plant (SQN) soil-supported structures which reflect a degree of conservatism sufficient to envelope the higher seismic levels associated with the 84th percentile earthquake. No further effort is required. ,

2. Safety-related piping systems - The reanalysis of selected systems effectively represented a reevaluation of all safety-related piping systems. From a review of all . safety-related piping systems, those systems with the highest ratio of stress resulting from combined leads to the corresponding allowable stress were selected for reanalysis to the 84th percentile earthquake. With these most critical systems having been found acceptable, it is reasonable to conclude that the remaining systems are at least equally acceptable.

The reevaluation of the piping systems and the conclusion that they are acceptable against the 84th percentile earthquake applies equally to all interfaces of the piping systems with safety-related equipment.

The piping reevaluation included confirmation that the original criteria for the seismic qualification of the pipe-supported equipment (valves, strainers, etc.) was not exceeded by the 84th fercentile earthquake. It was further confirmed that the original criteria for piping systems nozzle loads imposed on floor-mounted equipment such as pumps was not exceeded..-

3 HVAC ducting - Because of time limitations, TVA was able to only briefly touch on the consideration of HVAC cucting reevaluation during the March 1979 presentation. The criteria which dictates the

. ~ . . . . . . - . . - -

' installation and . support of the HVAC ducting reflects a degree of I conservatism which is more than sufficient to envelope the increased - T seismic levels of the 84th ' percentile earthquake. A more detailed " - ' '

l discussion to HVAC ducting and duct-mounted equipment will be included, i

in the remaining work for the followup program.

4. Safety-related equipment - The March 1979 evaluation and report to j .NRC addressed only selected items of mechanical equipment critical to
safe shutdown. In the followup program, TVA will continue and expand the presentation of equipment evaluation for 84th percentile earthquake as follows.
a. Consistent with the original guidelines developed with NRC regarding the scope of this reevaluation effort, the items of equipment to be considered will be limited to TVA-procured, balance-of-plant equipment. It is understood that the NSSS- i supplied equipment has been evaluated by NRC with the NSSS vendors I on a generic basis.
b. After review of mechanical equipment listing, TVA will include any critical items which were not covered in the March 1979 '

presentation.

c. TVA will provide a thorough presentation of critical Category I instrumentation and electrical equipment qualification to show that ,

it envelopes the 84th percentile earthquake. -

The completion of the TVA program of evaluation of critical items of equipment will provide a sufficient basis to form the engineering conclusien that the seismic qualification of all'elec-

.' trical and mechanical equipment critical to safe shutdown can be

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shown to be sufficiently conservative to envelope the P4th

Note: Tabulations of safety-related mechanical and electrical

, equipment to be considered in the reevaluation effort are included in the attached TVA correspondence. ~

Program Schedule TVA has committed to complete the equipment reevaluation program by

  • Harch 1, 1982, as reflected in SQN's operating license. To support this schedule,- the following milestones have been established.
1. Interim status - In September 1981, TVA will get in touch with NRC representatives en an informal basis to discuss the progress of the reevaluation and any problems which uight have been encountered. The advisability of a TVA/NRC interim meuting will be discussed and scheduled if considered appropriate.
2. Presentation of results - January 2, 1982, has been established as the target date for completing the reevaluation effort. By this date, TVA will get in touch with NRC representatives to coordinate a meeting for the presentation of equipaient reevaluation results. A meeting held as i soon as possible af ter this date would leave time to resolve any '

r questions or concerns rega'rding the presentation of reports.

l 3 The effort will be completed by March 1, 1982.

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un a t.u. n ARS GOVERN 31ENT ATTACI: MENT A1 *

~bemOYd15dum TENNESSEE VALLEY AUTHORITY '

'CEB '800826 4007' -

TO  : Those listed FRO)!  : R. O. Barnett, Chief,' Civil Engineering 3 ranch, W9D224 C-K DATE  :

AUG2 61980

SUBJECT:

SEQUOYAH NUCLEAR PLANT - SEISMIC REEVALUATION OF SAFETY ,RELATED EQUIPMENT

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Reference:

Supplement No. 2 to the Safety Evalua' tion Report, NUREC-00ll, dated August :,, 1980.

As outlined in the reference TVA has co=mitted to reevaluate the seismic qualification of safety-related electrical and mechanical equipment against the more severe 84th percentile earthquake. This effort will inclu'de all equipment necessary for decay heat removal. Civil Engineering

. Branch's (CEB's) Component Qualification Section will be oponsible for' the technical reevaluation; however, your assistance'will be required to accomplish,this task in a timely manner. '"

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The ~ pacing ites for this effort is, of course, the definition of specific ,

iten.s of electrical and mechanical equipment critical to the decay heat r_epoval process. It is requested that the Nuclear Engineering Branc,h_ (NE3)

/vith necessary support from the Electrical Engineering Branch (EEB1/

provide this detailed list of equipment. In order to provide a timely response to the Nuclear Regulatory Commission (h*RC), the requested ...

equipment lists should be provided to CEB's Component Qualification Section by October 15, 1980. If, for any reason this target date cannot be net, advise CEB as to your proposed alternative completion date. ,

A large portion -of this task will be that of retrieving the seismic qualification documentation for each iten of equipment from procurement contract files. It is requested that the Mechanical Engineering Branch (MEB) and EEB each designate an individual to coordinate the qualifica-tion report retrieval effort among the various procurement organizations.

Any comments or questions concerning the above should be directed to F. H. Coleman at extension 2157. .

R. O. Barnett F. W. Chandler, W3Cl26 C-K C. A. Chandley, W10D224 C-K G. F. Dilworth, W10Cl26 C-K E4B37 C-K '

k ba R. W. Cantrell, 204 GS-K (2)

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f.i M3 %01126 252 ATTACHMENT A2 .

- R. O. Barnett, Chief, Civil Engineering B anch, W9D224 C-K 4  % -

John A. Raulston, Chief Nuclear Engineer, W10C126 C-K , x El_

N 881S8 -

801204E0039 SEQUOYAH NUCLEAR PLANT - SEISMIC REEVALUATION OF SAFEIT-RELATED EQUIPMENT

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Reference:

Tour memorandus to Those listed dated August 26,1980 (CEB  !

800826 007) - -

Your me=crandus requested a listing of electrical and mechanical

. equipment critical to the decay heat removal process as input to the g seis=ic qualification reevaluation program for SCN. The attachment presents a table of safety-related =echanical equipment to be used in M- ,

defining the extent and detail of the program. Thi's listing includes d 'l

- only major mechanical equipment and does~not include NSSS equipment, .

other than a systems list, according to your guidance. Also, it f should be noted that the listing does not individually specify certain c1=ponents (e.g. , valves and da=pers) within an identified system.

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We are requesting by this memorandum that EL supply a corresponding listing of major electrical equipment necessary to support the N -

identified mechanical equipment.

More detailed and specific mechanical and electrical equipment 1ists -

g can be generated, if required.

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&h John A. Raulston -

yp RSM:PJB Attachment .

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(M R. W. Cantrell, 204 GB-K (2)

F. W. Chandler, W8C126 C-K - Please provide the electrical

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. equipment list as discussed above.  ;

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  • l System Component ,

Drawinc.

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Auxiliary Power 5.9 kV/480V Press" Htr Transformers l A-A 45N234 1B-B 45H234

" 45H234

. 2A-A 28-8 45H234 480V Distribution Panel "

Bds for Press Htr lA-A 18-B ,

2A-A 28-B 120V AC Vital Control Static Inverter 1-I,1-II,1-III,1-IV 45N230 Power 2-I, 2-II, 2-III, 2-IV 45N230 Instr. Pwr Bds. 1-I, 1-II, 1-III, 1-IV 45N230 2-I, 2-II, 2-III, 2-IV 45N230 125V DC Vital Control Battery Chargers I & II, spare 1 45H230 Power III & IV, spare 2 45N230 Transfer Devices for Batt Charcers I & II, 45N230 (2) spare 1 Transfer Devices for Batt Chargers III & IV 45H230 (2) spare 2 Vital "

Batteries I & II 45N230 III & IV 45N23.0 Vital Batt Bd. I & II 45N230 III & IV 45N230 Electrical High Voltage Power Penetrations Penetrations Nuclear Instr. System Penetrations

. Control Rod Pos. Ind Penetrations low Voltage, Power Control, and Indication

. Penetrations

  • Thermocouple Penetrations , ,

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System Component

. ix 0rawine-Auxiliary Power 6.9 kV Shutdown Board Logic Panels 456S7005 ,

6.9 kV Swgr for New DG .

45N728 6.9 kV Air Interrupter Switch for DG 6.9 kV Shutdown Board 1A '

45N724-1 6.9 kV Shutdown Board 1B ._____.

45N724-1 M 6.9 kV Shutdown Board 2A 45N724-2 6.9 kV Shutdown Board 2B 45N724-2 480V Shutdown Board 1Al-A r. 2Al-A . . 45N749-1  %

1A2-A &. 2A2-A ~45N749-2 C.C3 181-B & 281-3 45N749-3.  %

480V Rea:. tor Mov Bd 1 Al-A 182-8 & 2B2-B 45N749-4 45N354-Wl 181-B - 45N366

-Ql 1A2-A 45N364 gl 182-8 45N366 2Al-A 45N368 D 2B1-B 45N370 Q 2A2-A 45N36B CL., l 282-8 45N370 g 480V Reactor Vent Board 1 A-A 45N380 18-B 45N380 2A-A 45N382 28-B -

45N382 480V Control & Auxiliary Gidg Vent Bd 1Al-A 45N383 1B1-B 45N384 1A2'-A 45N333  ;

182-B 45N384

" I 2Al-A '

45N385

"- 281-B 45N386

" g 2A2-A 45N385 '

2B2-B 45N3SS i 480V Diesel Auxiliary Board 1Al-A .

15N216' '

1A2-A 15N216 i 181-B 15H216 3

, 132-B 15N216 2Al-A 15N218 l 2A2-A 15N218 281-B 15N218 l 2B2-B 15N218

. 6.9kV/480V Shutdown Board Transfomerr,1 Al-A 45N332

" l 1A-A 45N332 "E

1A2-A 45N332 1 181-B 45N33E IB-B 45N332 -

, ., 182-B 4bN332 2Al-A 45N332 2A-A 45N332 I 2A2-A 4EN332 '

281-B 45N332  !

2B-B 45N332  ;

. 2B2-8 45N332

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SEQUOYAH NUCLEAR PLANT

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Mechanical Safety-Related Equipment List , ;

System . Component . Drawing

47W801-1 Relief Valves 47W801-1  : .

. *SG 3~owdown Isolation Valves 47W801-2 ,,-

47W803-1 .

Motor-Driven Pu=ps 47W803-2 Valves 47W803-2

  • Chemical Volume and Control NSSS Supplied
  • Safety Injection NSSS Supplied (Except Storage Tank 47W811-1)
  • Upper Head Injection NSSS Supplied

Heat Exchangers 47W812-1

    • High Pressure Fire '

Protection Pwsps 47W832-1 Valves 47W832-1

. Strainers -

47W832-1,

.

  • Ice Condenser Dcors and Passive Portion of ,.,

System which is Required for LOCA 47W814-2 Control Rod Drive NSSS Supplied

  • Diesels Generator D-G Manual Engine D-G Manual D-G Msnual C@lers ,
  • Essential Raw Cooling -

Water (See note 6,) Pumps 47W845-1 & 5 Valves 47W845-1 to 5 Traveling Water Screens 47W845-1 & 5 Screen Wash 47W845-1 & 5 Strainers 47W845-1

  • Control Air Auxiliary Air Compressors 47W848-1 i

After Coolers 47W848-1 Air Receivers -

47W848-1 Air Dryers 47W848-1 Filters 47W848-1 Valves 47W848-1

. Tanks 47W839-1 l Filters 47W839-1 Valves 47W839-1

, Towers & Fans 47W845-1 Traveling Screens & Screen Wash 47W845-1 Valves 47W845-1

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. , l System Component iDradini

  • Standby Diesel Oil 7-Day Tanks 47W8401 1 Day Tanks 47W840-1 Motor-driven Pumps .. 47W840-1 Engine-driven Pumps

. Filters 47W840-1 Valves 47W840-1

  • Spent Fuel Pool Cooling NSSS Supplied

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Thermal Barrier Booster Pu=ps 47W859-2 M

  • Main Control Room A/C See Note 1 47W865-3 480-V Bd. Room 4/C See Note 1 47W865-6 g *Elec.* Bd. Room A/C See Note 1 47W865-7
  • Shutdown Bd. Room A/C See Note 1 '

47W866-8 and Ventilation 47W866-3 O Air Return System

  • 480-V Transformer Rm Ventilation Exhaust Fans 47W866-3 Intakes ~

47W866-3 Dampers 47W866

  • Vital Battery Rm Exhaust Fans ,

47W866-3 Ventilati.,a Dampers 47W866-3 Emergency Gas Treatment System Fans 47W866-1

, Filters 47W866-1 Heaters 47W866-1

. Demister 47W866-1 Aux Bldg Gas Treatment System . Fans 47W866-10 Filters Heaters Dampers Vacuum Relief Demister

  • T'urbine-driven Aux. Feed
  • Control Bldg. Ventilation (Pressurization, Emerg, i

Pressurization, Air l Cleanup, Battery

! Exhaust) . Facs 47W866-4 l . Dacpers 47W866-4 i .' Fil'ters .47W866-4 Fire Dampers 47W866-4 l NSSS Supplied l Waste Disposal System t

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l System Component Drawing' l

  • Safety Feature Equipment .

Coolers (Serves RHR, -

SIS, CCS, EGTS, Boric .

Acid Transfer, CS,S, '

AFW, SFPCS, and Centrifugal Charging Pumps and Pipe Chases and Penetration Rooms) Air Handling Units 47W845-4

    • Flood Mode Boration and Makeup (See Note 2) Pumps 47W809-7

. Tank 47W809-7 Valves 47W809-7 Containment Vaccu:a -

Relief

  • Valves 47W866-1 Miscellaneous Cat.'I cran's#

Fuel Transfer Tube Fuel Transfer Conveyor New and Spent Fuel Racks -

. Pressure Confining Doors

Watertight Doors and Seals ,

RER Sump Manways and Seals ERCW Personnel Access Doors and Scals

, Containment Personnel Access Doors and Seals Missile Barriers for A/C Enclosures

, Aux. Bldg. RR Access Hatches and Seals Containment Equipment Access Hatch and Seal Escape Hatches and Seals Shield Door and Enclosure

  • Seal Between Ice Condenser and Containment Vessel Railroad Access Doors Spent Fuel Pit Bridge Crane Manipulator Crane
  • CCW Discharge Gates and Roists Note 1: The total system should be included; i.e., AH1's, chillers, valves, fans, dampers, filters, pumps, compressors, condensers, etc.

Note 2: Only a limited seismic requirement is applicable to this system.

Note 3: The listing does not include containment isolation valves in l nonsafety-related systems. These valves are also safety-related.

l Note 4: This list does not include monitoring equipment for radiation and neutron flux, nor does it include the reactor protection system.

P0OR ORIGINAL

Note 5: The CO 2 and lube oil ventilation, fuel oil transfer roco exhaunt '

corridor and toilet room ventilation, and unit heaters 'dodco! ' ,

perform a primary safety function. -

Note 6: This includes the ERCW pumps, valves, strainers, and traveling water screens at the intake pumping station, as well asthe ERCW intake station, until the barge impact concern for the ERCW intake station is resolved. This equipment at the~ intake pu= ping station may be necessary if there is barge impact of the ERCW intake station.

However, barge impact need not be considered situltaneous with a

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      • Needed for decay beat removal only in event of fire-caused loss of the cables for ERCW intake prior to completion of ECN L5298.

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, . ATTACH' MENT A3 e 4

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UNITI:D STATES CnVERNMENT ,

.TesEsseM49.!sMacfnE;rdri-Memorandum ,

R. O. Barnett, Chief Civil Engineering Branch, W90224 C-K T'S ' J. A. Raulsta i, Chief Huclear Engineer, W10C126 C-X rniin  : F. W. Chandler, Chief. Electrical Engineering Branch, W3C126 C-X DATE  : February 26, 1981 ,,

i 81030580417 O ,

81*H M T: SEQUOYAH NUCLEAR PLA'iT SEISMIC REEVALUATION OF SAFETY-RELATED EQUIPMEtiT Refer to J. A. Raulston's memorandum to R. O. Barnett dated November 26, 1980 (NEB 801126 252), concerning Balance of Plant (BOP) equipment to undergo seismic reevaluation as a result of Safety Evaluation Report (SER) requirement. ,

The referenced tremorandum requested the Electrical Engineering Branch i to supply a listing of major electrical equipment necessary to support the mechanical equipment identified in the reference. The major BOP '

electrical equipment is shown on the attached list. Not listed are motors since they are considered part of the driven equipment for seismic evaluation purposes'and are assumed to be Itsted with the driven -

equipment. _

All BOP safaty related instruments are included fri one of the "

three following categories: '

1. Main Control Panel Mounted
2. Local Panel (racQ Hounted
3. In-line Mounted Per discussions between CEB's F. H. Coleman and our B. O. Buchanan, no further detailed listing is necessary for the instru.tentation.

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