ML18191A234

Attached WPPSS Nuclear Project No. 2 Suppression Pool Current Design Drawings, Which Do Not Reflect Any Design Changes That May Be Needed to Accommodate Loads Resulting from Pool Dynamic Forces During SRV Actuation or LOCA

ML18191A234
Person / Time
Site:	Columbia
Issue date:	07/25/1975
From:	Strand N Washington Public Power Supply System
To:	Parr O Office of Nuclear Reactor Regulation
References
G02-75-210
Download: ML18191A234 (9)

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NRC DISi IBUTION FOR PART 50 DOCKET MATERIAL FROM HFPSS Richland,~Plashing ton (TEMPORARY FORM):"

7~25~75 7-31-75 DATE OF DOC DATE REC'D LTR CONTROL NO: 4i FILE TWX RPT OTHER TO:

Olan D, Parr ORIG 1 Signed CC OTHER SENTNRC PDR SENT LOCAL PDR CLASS UNCLASS PROPINFO XXXX INPUT NO CYS REC'D 1

DOCKET NO:

50-397 DESCRIPTION:

Ltr. notarized 7-25-75 ~ ~.Re,'out:.ltr.'-17-75, 4-23-75 ~.6 their ltr. 6-5-75.....trans the following......

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PLANT NAME.

Hanford 0

2 ENCLOSURES:

Furnishing"Mark II Containment info. Current D

'esign Drawings"... Providing info re

'ested by LOCA question 8 1 & portions of uestion 1 6 5 6including info. to rema

'l:tion of SRV g 1

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FOR ACTION/INFORMATI N BUTLER (L)

W/ Copies CLARK (L)

Ml/ Copies

/ PARR (L)~

Ml/ Copies KNIEL (L)

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W/ Copies KNIGHTON (E)

W/ Copies YOUNGBLOOD W/ Copies REGAN (E)

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W/ Copies SPIES W/ Copies (E) ~LPM W/

opies INTERNALDISTRIBUTION QNRC PDR OGC, ROOM P-506A GOSSI CK/STAF F CASE GIAMBUSSO BOYD MOORE (L)

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P. COLLINS DENISE REG OPR FILE 5 REGION (2)

MIPC TECH REVIEW SCHROEDER MACCARY

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~ Qsk P. O. BOX 868 Docket No. 50-397 3000 GEO. WASHINGTON WAY RICHLAND. WASHINGTON 5

IVV%A I Ico July 25, 1975 G02-75-210

)4 8.888I Mr. Olan D. Parr, Chief Light Hater Reactors Project Branch 1-3 Division of Reactor Licensing U. S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

WPPSS NUCLEAR PROJECT NO.

2 MARK II CONTAINMENT INFORMATION CURRENT DESIGN DRAWINGS g 0'"

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Reference:

1)

Letter, JJ Stein to HR Butler, BWR Mark II Containment-Additional Design Information, dated June 5, 1975 2)

Letter, WR Butler to JJ Stein, Suppression Pool Hydro-dynamic Loads during LOCA, dated April 17, 1975 3)

Letter, HR Butler to JJ Stein, Pool Dynamic Loads due to Relief Valve Operation, dated April 23, 1975.

Dear Mr. Parr:

As promised by our Reference 1, attached are drawings of the WPPSS Nuclear Project No. 2-,suppression pool as currently designed.

These drawings do not reflect any changes, in design that may be needed to accommodate loads resulting from pool dynamic force's during safety/relief, valve (SRV) actuation or LOCA.

It is intended that these drawings provide the information requested by LOCA question 81 (Reference

2) and portions of SRV questions kl and P5 (Reference 3).

Additional information has been included to answer the t emaining portion of SRV question 81.

Fifteen (15) copies of the attachment are being submitted for your review.

Very truly yours, NOS:GLG:lc Attachments N. 0.

STRAND Assistant Director Generation 8 Technology cc:

DJ Anderson - Bonneville Power Administration JJ Byrnes - Burns 8 Roe, Inc.

FA MacLean - General Electric Company J

Forman - Burns 8 Roe, Inc.

JJ Verderber - Burns 8

Roe, Inc.

Letter, NO Strand to an D. Parr, entitled "Hark II tainment Information

'urrent Design Drawings," dated July 25, 1975, Letter No. G02-75-210.

STATE OF WASHINGTON )

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ss COUNTY OF BENTON

)

N. 0.

STRAND, Being first duly sworn, deposes and says:

That he is the Assistant Director, Generation and Technology, of the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein; that he is authorized to submit the foregoing and knows the contents thereof; and believes the same to be true to the b

of his knowledge.

DATED 1975 N. 0.

STRAND 1975.

On this day personally appeared before me N. 0.

STRAND to me known to be the individual who executed the foregoing instrument and acknowledged that he signed the same as the free act and deed for the uses and purposes therein mentioned.

GIVEN under my hand and seal this ~Su day of Not ry Public in and fo the State of Washington Residin at > ~~A

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'NUCLEAR SYSTEM SAFETY/RELIEF VALVES No. of Safety/Relief Valves Spring Set Pressure si ASME Rated Capacity at 103K Set Pressure lb/hr each 2

4 4

4 1130 1175 1185 1195 1205 851,000 884,000 892,000 899,000 907,000 18 Total (all connected for REVAB, 7 connected for autoblowdown*,

12 connected for prompt relief trip)

All of these valves are equipped with pneumatic operators for automatic overpressure relief operation at the following pressures:

uantit Relief Pressure Controller Set Pressure si 2

4 4

4 4

1076 1086

'096 1106 1116 II.

SAFETY/RELIEF VALVE OPERATING CONDITIONS l.

Overpressure relief operation.

The valves are opened automatically to limit the pressure rise and to prevent operation of these valves in the overpressure safety valve mode.

2.

Overpressure safety operation.

The valves function as safety valves and open (self-actuated operation if not already automatically opened for relief operation) to prevent nuclear system overpressurization.

3.

Depressurization operation.

The required number of valves are opened automatically as part of the core standby cooling system (CSCS) for events involving small breaks in the nuclear system process barrier.

4.

Prompt relief trip operation.

A scheduled number of relief valves are tripped open automatically following initiation of a turbine generator trip.

This function is available only above 67/ of rated power.

5.

Relief Valve 'Augmented Bypass (REVAB) Operation.

All relief valves are tripped open and reactor power, level reduced allowing a full load rejection (breaker trip) without a reactor scram.

This function is available only above 30Ã of rated power.

• This provides sufficient flow capacity to satisfy-'automatic depressurization requirements assuming that one valve fails to open.

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'III." SAFETY/RELIEF VALVE DISCHARGE LINES As presently designed (see the attached drawings) the 10-inch relief valve lines are routed into the wetwell through 18 oversize drywell to wetwell downcomers.

It is anticipated a quencher (perforated cross) configuration will be used to mitigate the relief valve loading on the suppression pool walls.

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