ML18043A951

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Summary of 790614-15 Site Visit of SEP Seismic Review Team. Forwards Util Supplemental Response to Seismic Question, Item 2.4,preliminary List of Equipment to Be Evaluated Per SEP Topic III-1 & Addl Info Required Re Seismic Resistance
ML18043A951
Person / Time
Site: Palisades Entergy icon.png
Issue date: 07/19/1979
From: Silver R
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
TASK-03-01, TASK-03-06, TASK-03-07.B, TASK-3-1, TASK-3-6, TASK-3-7.B, TASK-RR NUDOCS 7908170506
Download: ML18043A951 (21)
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MEETING

SUMMARY

DISTRIBUTION

@eD NRC PDR

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Loca 1 PDR ORB #2 Reading NRR Reading H. R. Denton E. G. Case D. Eisen hut R. Vollmer W. Russel 1 D. Crutchfield L. Shao V. Noonan W. Gammil 1 A. Schwencer T. Ippolito R. Reid B. Grimes G. Lainas P. Check J. Miller R. Clark F. Pagano G.. Knighton Project Manager - R. Silver J. Wetmore*

OELD OI&E (3)

H. Smith R. Fraley, ACRS (16)

NHC Participants J. R. Buchanan TERA...

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Docket.No.

50~255

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  • LICENSEE:.consume,rs.Ppwer CQmpany I.

FACILITY:

Palisades* Plant

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SUBJECT:

SITE VISIT OF SYSTEMATIC" EVALUATION. PROGRAM SEISMIC' REVIEW.

TEAM TO* PALISADES PLANT

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Memb.ers of th~ Nuclear Regulatory Commission. (NRC) staff and its consultants

,~~y;y-fs):teif.:.the PB:lis~d~s Plant on June _14-15~/1"1979, for a.systematic Evaluation

~/Program (SEP) Seismi;c Review Meeting. _Attachment 1 is a 1 ist of the attendees.

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Pu.~ing the morning of J,une 14, CPC personnel descri'bed the plant arr~ngement

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and showed the location of t,he components, systems and structures ident1fted

      • in the N*Rc letter to CPC*dated May 29,' *1979, This was done by viewing slides of plant layout drawings and pip~ng *and instrumJ;!nt tliagrains.*
  • Infonnation.to Sl1PPlement their submitta 1 of June 8,. 1979, was a.l so provided (Attachments ?.

and 3). Then a plant tour was conducted so that the.NRC staff *and its consultants could obs~rve the structures and supports for piping, mechanical and electrical components associated with those *systems identified in t.he NRC letter as being required for safe shutdown in th~ event of a postulated seismic event. The tour did not include the interior of the Containment Building or 'the charging

  • pump rooms becaus~ of ~ealth~lhy:s:1e~control_ c_o_n~ideratioris...

-~On June 15, the NRC *staff an_d. its consultants discus.sed *wi_th CPC the additional

.documentation and infonnation th.at would _be necessary to* veri~y t~e seismic resistance capability of the Ri'alisades Plant. *The* list of items.developed*_

and discus*sed durihg the meeting. is gi'ven in..1-\\tt.achment 4.* '

Attachments:.

  • As stated cc,w/attachments:

See next page *

.n Q:rigi~al Signed by..

R" chard D. S-ilv-e:t:*"

_1 Ric~ard o. S:ilver, Project 'Manager.

Operating Reactors Branch #2

  • Div{s1on of.Operating Reactors REGULATORY DOCKET fl.LE COPY BURNAMll.. ~/~h *--~~:~~~P..

DLZiemann

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NUC POllM 318 (9-76) NB.CM 0248

  • u.a. Q~VBRNMBNT P'RINTING OP'... ICB: 1111 - z*it -111*

cc w/attachments M. I. Miller, Esquire Isham, Lincoln & Beale Suite 4200 One First National Plaza Chicago, Illinois 60670 Mr. Paul A. Perry, Secretary Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201

--~udd L. Bacon, Esquire Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 M)tron M. Cherry, Esquire Suite 4501 One IBM Plaza Chicago, Illinois 60611 Kalamazoo Public Library 315 South Rose Street Kalamazoo, Michigan 49006 Mr. David Bixel Nuclear Licensing Administrator Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 2 -

I I

PALISADES SEISMIC SITE REVIEW MEETING LIST OF ATTENDEES Consumers Power Company G. Cashell R. Marusich E. Wong K. Berry R. Nelson W. Beckius Becbtel T. Johns CJl K. Chao F. Hsiu S. Kapur C. St. Onge D. Riat P. Smith EDAC D. Wesley R. Kennedy Lawrence Livermore Lab T. Nelson Woodward-Clyde J. Stev~nson Combustion Engineering T. Nathan D. Peck D. Tolli J. Davison KM c~ Ilic.

R. Schaffsta 11

.. NRC P. Chen C. Hofmayer H. Levin R. Silver D. Segal T. Cheng

~ ATTACHMENT l

~.

ATTACHMENT 2 Palisades Nuclear Plant Supplement to the Response to NRC Seismic Question, Item 2.A The entire seismic analyses process for the Palisades Nuclear Plant containment and internal structures reflected the then state-of-the-art, as well as the design requirement at various stages of the engineering work.

At the preliminary design stage, in early

  • 1967, the con-tainment shell and internal structure were modeled separately as* a single stick, lumped mass, fixed base model.

The spectral response technique and absolute sum of the model responses wer--e-- --.. _ *-.

used to generate structural design forces.

(~hese forces were used in the structural design.)

A summary of the response envelopes for the fixed base containment building model are shown in Figure 1.

A seismic analysis model considering soil-structure interaction was developed later, this model and resultant forces envelope were presented in Palisades FSAR, Section 5.1.3, and is dupli-cated in Figure 2.

This modified model incorporated the trans-lational and rocking soil springs and lumped the total masses of the internal structure to the base of the containment.

The final seismic analysis for the Palisades Plant containment and internal structure was completed in June, 1969.

The final seismic analysis considered both the soil-structure interaction and the coupling effect between the containment shell and the int~rnal structure.

This analysis also generated the floor response spectra for the purpose of equipment quali-ficat~on.

A summary of the force envelopes for the contain-ment shell for the design earthquake (OBE) are shown in Figure 3.

The response to NRC seismic questions item 2.A was prepared solely based on the final seismic analysis.

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Equipment Primary Coolant System Reactor Vessel Reactor Core & Internals Steam Generator Tube Side Reactor *coolant Pumps (Casing & Internals)

Pressurizer & Surge Line Reactor Coolant Piping Pressurizer Spray Lines Spray Valves (Required to operate)

Reactor Coolant Pump Seals Pressurizer Relief Valves (Part of Pressure Boundary) 9*

ATTACHMENT 3 List Palisades Pr osed Seismic Verification to be ~erformed under SEP Topic III - 1 Earthquake Alone x

x x

x x

x x

x x

x Earthquake plus Loss of AC x

x x

x x

x x

x x

x June 12, 1979 Rev 1 Preliminary List F.arthquake

-plus LOCA and loss of AC (see note) x x

x x

x x

x x

x Pressurizer Safety Valves x

X (Required to open and close) x Piping from Pressurizer to the Safety and Relief Valves Reactor Coolant System Drain Lines to First Isolation Valves including this Valve LT-0103, LI-0103 Pressurizer Wide Range Level PT-0102 A thru D and other components which comprise RPS Trip on Pressurizer Pressure PT-0103, PI-0103, Pressurizer Wide Range Pressure TE-0121A, Band TE-OlllA, B TT-0115, TT-0125, TR-0115 TP.-0125, Primary Coolant System Temperature x

x x

x x

x x

x x

x x

x x

x x

x x

x Note CPCo does not agree that this is a proper combination of events for consideration in SEP.

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Equipment (Primary Coolant System cont'd)

PDT-0112AA thru PDT-0122DD and Components of F.PS Trip on Low Flow Chemical and Volume Control System Boric Acid Tanks T-53A &

T-53B Boric Acid Pumps P-56A &

P-56B Boric Acid Gravity Feed Valves M0-2169 & M0-2170 Piping, letdown line to CV-2001 Piping downstream of CV-2003,

-2004, & -2005 via letdown HX to outside ~ntainment barrier Piping from Boric Acid ta.nks and pumps, and down..:

stream to Charging Pump Section Piping from M0-2087 near Volume Control Tank to Charging Pumps Piping from Charging Pumps via Regen. HX to valves CV-2113, CV-2115, CV-2117 Shell Side of Regenerative Heat Exchanger

  • Letdown Heat Exchanger Tube Side Boric Acid Filter Piping from CV-2113,-2115, and -2117 to the Primary Coolant System Earthquake Alone x

x x

x x

x x

x x

x x

x Earthquake plus Loss of AC x

x x

x x

x x

x x

x x

x x

June 12, 1979 Rev 1 Preliminary List Earthquake

-plus LOCA and loss of AC (s~~ note pg 1 x

x x

x x

x

Equipment (Chemical and Volume Cont~ol System cont'd)

Charging Pumps Bre.nch Piping up* to first normally closed Valve Actuation to get Boric Acid from Tanks to Charging Pumps (actuate Boric Acid Pumps, open either M0-2140 or CV-2155, actuate Charging Pumps, open CV-2115 and -2113 open t-D-2170 and -2169)

Piping from Charging Pumps to Auxiliary Spray Line via CV-2ll7 Actuation for CV-2117 FE-02l2, FT-0212 Charging.Line Flow Safety Injection System Safety Injection Tanks Piping from SI Tank Check Valves to SI Tanks Piping from the Safety Injection Tanks Check Valves to Reactor Coolant System SI Tank Check Valves Piping in the Low Pressure and High Pressure Safety Injection Pumps to Motor Operated Valves Containment Spray.Nozzles &

Headers Piping from High Pressure and Low Pressure Safety Injection System Motor Operated Valves to the Reactor Coolant System Earthquake Alone x

x x

x x

x x

x x Earthquake plus Loss of AC x

x x

x x

x x

x x

June 12, 1979 Rev 1 Prelimary List Earthquake t>lus LOCA and loss of AC (see note pg 1:

x x

x x

x x

X*

Eouipment (Safety Injection System cont'd)

Motor Operated Valves and Check Valves in this Piping Safety Injection Tank Vent and N2 Lines from Tank to First Isol~tion (NC) Valve Branch Lines up to and including first normally closed Valve All Components Piping and Valves Within the High Pressure and Low Pressure Safety Injection and Containment Spray System Including the Shutdown Cooling Heat Exchangers and Containment Sump not covered above.

SIRW Tank Piping from SIRW Tank to SIRW Tank Heat Exchanger Tube Side o~ SIRW Tank Heat Exchanger All Components required'to Actuate the Valves Operated*

by High Pressure Compressed Air Actuation of the High Pressure Safety Injection Pumps, Low Pressure Safety Injection Pumps, Containment Spray Pumps SIRW Tank Level Actuation Signals and Actuated Components June 12, 1979 Rev 1 Prelimary List Earthquake Alone Earthquake Earthquake

-plus LOCA and plus Loss of AC loss of AC (see note pg 1 X (RC Boundary only)

X(only those portions needed for long term cooling)

X(only that needed for long term cooling) X (RC Boundary X only) x x

X(only those X

portions needed for long term cooling) x x

x x

X (only that X

needed for long term cooling) x

~iP!llent (Safety Injection System cont'd)

NaOH Tanks and Piping Shutdm;n Cooling Piping from Rea~tor Coolant 5ystem to Safety Injection Syst.em Shut.down Cooling Isolation Valves (including valves)

Shutcown Cooling Piping

~=== t~e Isolation Valve to Lew Pressure Safety

  • Injection Pumps FE, FT and FI-0308 to 0314

~.-f'<>h* TnjeC'tion Flow F/F-3025, HIC-3025B Shutdown Cooling Flow Control Auxili~rv Feedwater System Auxiliary Feedwater Pump Turbine Driver Moto~ Driven Auxiliary FW Pum:p Piping from the Main Steam System to D:r':iver Auxiliary Feedwater Pump Turbine Driven Piping from the Condensate Storage Tank to the Auxiliary Feedwater Pumps and from the Auxiliary Feedwater Pumps to the Steam Generators Condensate Storage Tank (To first closed Valve)

F.artbquake Alone x

x x

x x

x x

x x

F.arthquake plus Loss of AC x

x x

x x

x

  • X x

x June 1, 1979 Rev 1 Preliminary List F.arthquake

-plus LOCA and loss of AC (see note pg 1 x

x x

x x

)*

Equipment (Auxiliary Feedwater System cont'd)

Sensors, Actuation Devices*

and Actuated Equipment Required to allow Auxiliary Feedwater to Enter Steam Generator (mainly CV-0736 and CV-0737, E/P-0736 and E/P-0737, actuation of available pump)

Piping and Components requ::l.red for Condensate Stroage Tank Heating and Primary Makeup Water Tank Hea~ing (Tank Side only)

Sensors Actuated Equipment and Actuation Devices Required to Allow Steam to Enter the Driver Isolation Valve -interfaced with Fire Fighting System (4" '." 29 - 0774FW)

Branch Lines to first normally closed Valve Piping from Auxiliary Feedwater Pumps to CV-0736 and CV-0737 Main Feedwater System Feedwater Piping from Steam Generator to and including Check Valve, and to CV-0736 and CV-0737 Main Steam System Main Steam System Piping From Shell-side of the Steam Generators to Main Steam Isolation Valves Earthquake Alone x

x x

.X x

x x Earthquake plus Loss of AC x

x x

x x

x X*

x June 12, 1979 Rev 1 Preliminary List Earthquake

-plus LOCA and loss of AC(se~ note pg 1) x x

Equipment (Main Steam System cont'd)

Main Steam Isolation Valves and Main Steam Isolation Valve Bypass Valves Atmospheric Dump Valves Air to Atmospheric Dump Valves Safety Valves Piping from Main Steam Line to the Safety Valves and Atmospheric Dump Valves LT-0751 A thru D, LT-0752 A thru D and other Components which comprise the RPS Low Steam Generator Water Level Trip Pl'-0751A thru D, Pl'-0752A thru D and other Components which comprise the RPS Low Steam Generator Pressure Trip and Close the Isolation Valves Pi.pi*ng from Top and ~ottom Steam Generator Blowdown Lines to and including Containment

.Isolation V~lves Hand Switches to Isolate these Valves Component Cooling Water Component Cooling Water Heat Exchangers-Shell Side Component Cooling Water Surge Tank and Circulating Pumps Earthquake Alone x

x x

x x

x x

x x

x x Earthquake plus Loss of AC x

x x

x x

x x

x x

x x

June 12, 1979 Rev 1 Preliminar:Y List Earthquake

'Plus LOCA and loss of AC(see note pg 1) x x

x

F.a.rthquake Eouipment Alone (Component Cooling Water cont'd)

Component Cooling Water System Piping from the Pumps to the 1-1,_,,1i*

Pv~l!angers, Shutdown Cooling Hea.t uchangers, a~d Engineered Safeguards Pump Seal Cooling up to Containment Isolation V3.Lre X

Sensors, Actuation Devices and Actuated Equipment Required to Ooen or Close Component Cooling Water Valves on SIS u1

~I...~W Tank Level and Required to Start Component Cooling Water Pumps on SIS (namely actuation of valve CV-0910, CV-0938,

_ v -rJ'-:137, CV-0945, CV-0946, cv-u~i3, cv-0947, cv-0948, CV-0960, CV-0951)

SP.~v5~~ Water System S~rvice Water Pumps Critical Service Water Piping Piping in non-critical Lines up to and including Isolation Valve SIS or Hand Switch Actuation of the Isolation Valve Tie Line piping between Service Water Pumps SIRW Tank Low Level and Hand Switch Actuation of Valves on Outlet to the Cc~~onent Cooling Water Heat Exchangers H9.!'.d. Switch Actuation of V2Jves in Line to Engineered

~..:.,'::c:*c:.3.rds Pump Seal Cooling ana i'..ngineered Safeguards

?:*:= C=olers (sts Actuation

.J....! * ~
:>...J I x

x x

x Earthquake plus Loss of AC x

x x

x x

June 12, 1979 Rev l Preliminary List F.a.rthquake plus LOCA and loss of AC(see note pg 1) x x

x x

x x

x x

Eguipment (Service Water System cont'd)

SIS Actuation of Valves in Lines to the Spent Fuel Pool Cooling, Radwaste Evaporators Branch Connections to the First Normally Closed Valve Diesel Generator Systems Components and Piping of the

-~Diesel Generator Fuel Oil(Day Tanks)

System, Lube Oil System, Starting Air System and Jacket Water System Sensors, Actuation Devices and Activated Equipment Required to Start Emergency Diesel Generators (Day Tanks)

Ventilation Systems F*ans, Coolers and Filters Comprising the Containment Air Cooling System, Including Ducts Hydrogen Recombiners Fans, Ducts; Coolers, and Filters which Comprise the Control Room, HVAC System Sensors, Actuation Devices and Actuated Equipment Figured for Closing Dampers which allow Air to flow to the Stack, or Recirculate Control Room Air.

High Pressure Air System Air Receivers for the Valves which are Activated by High Pressure Air (all in SIS)

Piping from the Air Receivers to the Valves Earthquake Alone x

x Earthquake plus Loss of AC x

x x

x June 12, 1979 Rev 1 Preliminary List Eartbqual:te l)lus LOCA and

  • loss of Ac(see note pg 1) x x

x x

x x

x x

  • Equipment 3amoling System P~essurizer Vapor Phase, Liquid Fua.se etnd Primary Cooling Sample Lines to and including the Containreent Isolation Valve Othe,. Sysi;ems Sensors, Actuation Devices and ActuateJ Equipment required for React.or Trip

.r2: i::.l:1es Actuated by High Containment Pressure or

~dia*i..ion.

h~~ r1ping associated with "Lil::

C~:it.ai!lillent Isolation Valves Containment Building & Penetrations Fa:::-.1 !':;;;l Storage Structure Fuel Racks Control Rods, Control Rod Drive Mecha;nis ms and Housing Auxiliary Building and Turbine Building (Pqrtions Containing above Equipment)

Power for all of the above Components (Switchgear, Control Boards, Batteries, Penetrations, etc)

Earthquake Alone x

x x

x x

x

x x

x x

x x

June 12, 1979 Rev 1 Preliminary List Earthquake

-plus LOCA and loss of AC (see note pg 1:

x x

x x

x x

x x

x x

. ATTACHMENT 4 ADDITIONAL INFORMATION REQUIRED TO DOCUMENT THE SEISMIC RESISTANCE CAPABILITY

~OF THE PALISADES FACILITY The NRC staff and its consultants have completed a review of the Palisades docket for information pertinent to the seismic design bases of the facility and its capability to withstand the effect of potential earthquakes.

The

~~~~mation currently on the docket is not sufficiently complete to adequately q1.1C
1ntify such capability. It is anticipated that pertinent information is avai1able from other sources such as the original NSSS, A-E, or plant files.

The following information is necessary to proceed with the seismic review; however, at this time it is not required that new information be generated to S3tisfy this request.

A. *Seismic Analysis and Design Criteria for Structures and Input to Equipment

1.

Building Models - The latest mathematical models for determining sei srnic response to input ground motions for the foll owing

2.

3.

4.
5.
6.

structures:

Containment building, including containment internal.

structure*

Auxiliary building Turbine building The seismic response profiles (acceleration, forces, moments, shears, displacements) actually used in design for the above buildings.

Actual floor response spectra used for the design of mechanical

  • and electrical equipment and fluid and electrical distribution
  • systems for the auxiliary building, containment building and containment internal structures.

Confirmation of soils design information; shear wave velocity, shear moduli, poissons r~tio, ultimate bearin~ ca~acity, density, Documentation supporting recent overturning and sliding analyses for the containment building and auxiliary buildings as referenced in the answer to question 2. B of a June 8, 1979 letter from D. Hoffman to D. Ziemann.

Structural details of the auxiliary~ turbine building tie at elevation 607' and the turbine buildi.ng foundation. *

- 2 B.

Seismic Qualification of Mechanical and Electrical Equipment and Fluid and* Electric Distribution Systems Seismic qualification documentation based upon. analysis or testing of actual equipment or similar equipment to' that installed at the Palisades facility is required.

. ~*.

Mechanical Components

~. ~ :.

1.

Control rod drive mechanism (arrangement details and or_iginal seismic design comput~tions) * *

2.
3.

Pumps - service water and ste~m drive auxiliary feedwater:.. ** *

(arrangement drawings including support and anchorage details or qualification data)

Heat exchangers - component cooling water and shutdown (arrangement drawings including ~uppbrt and anchorage details or qualification data)

4.

Tanks - a.

hydrazaline, sodium hydroxide, diesel generator day tank, component cooling water surge, boric acid storage (or eves)' :(arrangement drawing_s including support and anchorage details or original seismfc design computations)

b.

Structural drawings of the safety injection tanks inside containment including tank support details and floor support details 6r origi~~l seismic de~ign comput~tions

c.

Anchor bolt details of condesate storage tank

5.

Motor operated valves - typical weights and center of grav.ity for 1 11

, 2 11

, 3 11

, and 4 11 diameter lines Fluid Distribution Systems

6.

Original detailed seismic analyses, piping isometric dra~lings including support locations, support stiffnesses (or necessary drawings of supports to enable a.determination of support stiffnesses), valve locations, valve masses and center of gravity, and other pertinent details needed to independently verify and audit the seismic capability of the following piping systems.

b.

Residual heat removal line inside containment from the first motor operated isolation valve (nonna1ly closed} or check valve to the reactor coolant loop.

c. Component cool i'ng water line outside contafornent betwee.n the component cooling water heat e)C_changer header and the RHR heat exchanger including each branch 1 ine alo_ng the path.

Each branch line should be included up to the first isolation valve (nonnally closed) or check valve.

d.

Typical 1 11 to 4 11 diameter rigidly designed field run piping (approx. 100 1 )

El ectriea l Components Structural integrity of cabinets or panels :including support welds/

bolting and operability of equipment~

7. Control room panels
8.

C04, C06 panels

9.

AC, DC motor control centers l O~ Switch gear 11 ** Reactor protection system instrumentation (possible generic

~pplicability of CENPD-182)

12.

2400-480 volt transformers (arrangement drawings including weights, center of gravity and tie down deta i1 s or qualification data)

Electrital Distribution*system l3. Cable trays including late.ral supports Spec ia 1

  • Componeri ts
14.

Battery racks 0

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