ML19309G764

Forwards Pages for Draft Revision 8 to Design Assessment Rept in Response to 800428 Telcon.Pages Will Be Incorporated Into Next Amend

ML19309G764
Person / Time
Site:	LaSalle
Issue date:	04/29/1980
From:	Delgeorge L COMMONWEALTH EDISON CO.
To:	Bournia A Office of Nuclear Reactor Regulation
References
NUDOCS 8005070526
Download: ML19309G764 (6)

Text

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h Commonwealth Edi on 11, ./ One First Natienal Plaza. Chicago, Illinois 800507064 v Address Reply to: Post Office Box 767 v Chicago, Ilknois 00690 A April 29, 1980 Mr. A. Bournia Division of Project Management U.S. do lear Regulatory Ccr: mission Washington, DC 20555

Subject:

LaSalle County Station Units 1 and 2 Design Assessment Report (Rev. 8 - Draft)

Dear Mr. Bournia:

As discussed in our telephone conversation of April 28, 1980, I am forwarding certain pages frcm the subject report that were inadvertently ,

omitted when it was sutmitted by Reference (a) . These pages will be formally incorporated into the next amendment to the DAR.

If you should have any questions, please contact me.

Sincerely,

. & J&p L. O. DelGeorge Nuclear Licensing Administrator Attachment cc: J. S. Abel (CIro.)

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FARK !! C'.St:RS CROtfP 1.0An 03 p4ENDE N04 IPAD e.PECIFICATI M NRO REVIEW STATtJS TA SALI.E POSITIOtt 04 ACCEP TANCE CRY 1ERIA , ,

b) bedines Steam Fl'au Sinunoidal pressure fluctuation _ Acceptable Loa.fs adJed tr. local hydrostatic. Am-plitude uniform below went esit- . . .

linear attenuat ioen to pool surlace.

7.5 pai peak-te. peak asplitude.

5, 6 Its f requencies.

c) Chugging Loads Representative pressure fluc- Acceptable pending tuation talen from 4T test resolution of FS!

added to lesal hydrostatic. concerns.

- uniform loading .la s ietes am.-l i t ude uniform below curieli t ion vent esit-linear attenuation to pool surfac . +4.8 psi g sanimum overpressure. -4.0 ps t g

asixieum und. r pressure, 20-30 11: .

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,v'I f,M I - asys'setr ic loading 'ta n i euw .sw;. l i t ude spi i t are I.e l ow conJition v.* n t emit-linear atteneation to pool surface. 20 psi sosienne overpsessnie. -14 psi maai mes

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MARK 11 OWNERS CROUP

!#AD Oft PftE CMENON IDAD SPECIFICATION FRC REVIEW STATtS IA SALT.E POSITION 03 ACCEPTANCE CRITERIA IV. Secaadarv Losde - .

A. Sonic Wave Lead Negligible toad - none specified Acceptable , r

3. Cwpre s. a ve W.ve Load begligible Load - sione specified Acceptable C. Pws Swll Wave Load No generic load provided Plant trtique load Described in La Salle Closure Report specification and NRC review.

D. Seismic Stosh Load No generic load provided Plant emique load Described in La Salle Clesure Report -

specification and NRC review.

E.' Fallback load on Submerged Negligible' load - none specified Acceptable Roundary F. Thrust leads Meinentum balance Acceptabic

• _ e-C. Friction Drag LoaJs Standard triction drag calculatiens Acceptalele E on. Vents Y a[

= _T H. Vent Clearing Loads Negligible Lead - none specified Acceptable k I P -

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MARK II ry:L'iS CMO'JP loAS OF Pi? ?#-??).?D'e IAAD SIT !?ICM1M 1:t i: r rVI Ek' TATS A ?.U f" FO?! TIC *t 0 ; ACC7PTA7CE CRITEft tA FU;;CT!f NA!, 1:.t er i's tet 6 i il Aa erte*1e. Pd abaugh criteria s.ay be used in s ee cases if CAN.dl!21Y 3+n a t i on ( 7/ l

• 0 . t it. ! - ac c.e pt abi c .

• MASS-EL;;GT . Verify using F L4r / # c e -p: 6i r.

RLIJ AS*: F94 ft,D ANMJ . TIS P> ESS.

QULSI!T:S IM gsak bro,d.ning Acc ptable

1. 1Lb-2. FJ h-> tu tv used.

Mta-3, MLa-5 Closely spaced mades Acceptabic. ESSS scope uses modified sumation combined Per I.92 per ayproved CLSSAR. g n

MLB-l Dynamic analysis Acceptable Y methods acceptible S 5

MEB-2 OSF Damping - Level .:.

h A cr 5 Acceptable y

SSE Damping - Level di C or D "

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% ME8-6 Seismic slosh plant Acceptable

.. unique review MEB-7s and b load Combinations: Acceptable. Ses load combination table for Case #2 and 7 AP+SSE OBL+SRV MEs-8 i Functional capsbility See load cenbination table.

/ anJ piping acceptance craterna E=3 .

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G O O MARK II CTMRS CROUP IDAL Pt'ENO*'ENo1 LOAD SPECIFICATION MRC REVIEW STATtl% IA $4 25 PO*17tott ON Actf eTWF C9tTUrf A

1. N*SRV, To B Acceptable

2. N+SRV +0SE to B Ac ce pt a ble Approved GLSS/,R appronh used for NSSS.

3. N+SRV gg +SSE to C Ace-ptable

4. N+SRV, ,*0EE*ISA to C Accertable

5. N+SaV,,,+0tE+1aA to C . Acceptable

6. N+3RV, +SSE+18A to C Acceptable F. N+SSE+D3A to C Acceptable

8. N to A Acceptable

9. N*OSE to S Acceptable e

10. N+SRV +SSE+DBA to C Applied to containment structure only (See M C20.22 and 'f h LG a 5.2.4. ami letter to R. J. Mattson fro.a L. J. Soben $ @

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LSCS-MARK II DAR fTi

,B Event 3 is a stuck-open relief valve with the reactsr isolated from the main condenser and maintained at otarnting p;ccoure and temperaturo. All RIIR heat exchangec equipatat :s con-sidered operational in this case because if one heat er. changer is not available, the reactor may not remain isolat.d and pressurized. The bulk pool temperature acsux.ed in this event is the highest allowed while the reactor is maintaining pressure.

Event 4 is a controlled depressurization fre the, plant condition described in Event 3. This evaat deic.36ct:. c.tas the abilit'y of the plant to safely depressurize through a controlled transient from the limiting conditions. .

Event 5 is a controlled depressurizatica svecral ninuhes after the reactor isolation dencribed in Event 3. &le heat exchanger is considered unavailable because pc.er cporation

. [* ' in that condition is not prohibited. This cycnt d:mone.hrates the ability to depressurice the plant safely thrcugh a con-trolled transient with only partiel RIIP heat exch nyer -

equipment availability.

Event 6 is a rapid depressurization of the reactor rcJulting f rom actuation of the automatic depressurization system ( ADS) .

ADS actuation takes place at the time the reactor is scrammed.

Because this event takes place quickly, no heat exchangers are brought into operation. This event represents the most rapid energy release to the pool and demonstrates that the plant may be safely depressurized in this trianner without use of heat enchangers.

Event 7 is also a rapid depressurization via ADS but with "the reactor isolated and prescuri~ zed and wi.th a limiting.

pool temperatur'e condition. All heat exchanger equipment is placed in the pool cooling made 1/2 hour after scram but is considered unavailabic when depressurination begins.

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