ML20210T414

Notifies That Items 310.17 & 310.18 of Encl Round Two Questions Re Ownership & Control of Exclusion Area Requested for LWA Site Suitability Finding CP Review

ML20210T414
Person / Time
Site:	Satsop
Issue date:	02/11/1975
From:	Harold Denton Office of Nuclear Reactor Regulation
To:	Deyoung R Office of Nuclear Reactor Regulation
References
CON-WNP-1756 NUDOCS 8605300166
Download: ML20210T414 (4)

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EEqUESIED COMPLETION DAIIs January 24, 1973 EETIEW STATU51 AAB Continuing

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-Items 310.17 and 310.18 of the emelased questirme, pertaining to i

l omnesship and esotrol of the -1=i= area, are required for an 1

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WA ~ site suitability finding'as us11 as for the CP review. The l

1 tematador of the items are couad tus questions for the radiological

' safety review. The review of turbine missiles has not yet been

'eoepleted and'geestions en this subject will be forwarded at e

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- We believe the status of the eunership of the site is an open item J

uhtak may affeet the LWA site suitability.shbedule. In response

~ to. our first round queettens, (prepared in 'eonjunscion with OGC).

l the app 14= man states that the portion of the anslusion area.

including the mineral rights not required for plant soustruction j

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will not be sumed by the applicant. Logstag operations and tree farming will be permitted in the ase-owned area. The applicant

. states that hia-authority to determina~all activittee will be J

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. obtaiand by entertag into agreemmets with the land ownere u

-(ladividu41s, private corporatises, and the State of Washington)

.and through the granting of appsopriate easements. Copias of all essented asseensata will be submitted to the BBC as.they besons b

available. 'Is addittaa, the appli===a is earrently in negotiations

. with several land awasse to'abtain ownership of the prop =rty required for plant eenstruetten.. The applicant espects all land

_ purehases and ensaments for the~ emelusion ares to be soupleted by July 1975. OGC is belas requested to determine what information

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ACCIDENT ANALYSIS BRANCH 310.17*

State whether the mineral rights of the non-owned lands (2.1.2) within the exclusion area will be specifically included in the agreements and easements which you are obtaining for these lands in order to establish your a'uthority to determine all activities.

If these arrangements and easements do not include the mineral rights, describe the l

basis on which you can conclude that the authority required by 10 CFR Part 100 will be satisfied.

310.18*

Discuss the status of your negotiations with Grays Harbor (2.1.2)

County to obtain authorization to control traffic in the exclusion area in case of emergency on the county road (the extension of Keyes Road) which traverses the exclusion area. State whether this is the only county road in the exclusion area and, if there are other roads, identify thc= by locating thcc on a =ap and discuss the arrangements made to control traffic in the BPA trans-mission corridor through the exclusion area if this right-of-way is not under your jurisdiction.

310.19 It is indicated in Section 2.2.2.6 of the PSAR that the (2.2.2)

Army performs training flights in the vicinity of the proposed plants. Please provide a complete description of these and any other military ' flights that could bring aircraf t within 10 miles of the site. "This description 4

should include the location and width of the corridors, types of aircraft, whether and what types of ordnance is carried, accidents statistics for the aircraf t, qualifi-cation status of the pilots (1.e., fully qualified or student), controls kept over the aircraft from ground, and all other information necessary to estimate the pro-bability of an aircraf t undergoing an accident and af-fecting the safety of the plants. Provide an estimate of such probability and justify all assumptions made in the calculation.

310.20 Tour response to Q 310.13 is not satisfactory as there (6.4) still remains in the PSAR apparent inconsistencies re-garding control room leak tightness. Review the text of Sections 6.4 and 9.4 and clarify whether 400 cfm or 40 cfm inleakage at 0.25 inch w.g. is the correct value.

310.21 Provide the calculated doses for the design basis loss (15.4) of coolant accident based on your current estimate of accident meteorology conditions.

Indicate the contain-ment bypass leakage fraction used in your analysis and revise Table 15.4.1-1 and Appendix 15.3 to be consistent with this bypass leakage value.

In your analysis include l

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' Site suitability questions.

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310-2 310.21 credit for mixing only in 50% of the shield building (15.4) annulus volume between the elevations of the upper and (Cont'd.)

lower ventilation intake headers (as illustrated schema-tically in Figure 15.B-2). Credit for mixing in additional i

volume of the annulus could be obtained by raising the upper intake header to a higher elevation in the annu-i lus (and lowering the lower intake header, if possible)..

State whether you intend to increase the annulus volume available for mixing by moving the headers in the shield building annulus.

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• < NDTICE.0F PEBRUARY 25,-1975 NEBTING WI'!H WASHING 1M PUBLIC POWER

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- jSLPPLY SYSTEN REGARDING SITE DRAINAGE SYSTEM - WPPSS NUCLEAR PROJECTS'. i

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UNITED STATES g

NUCLEAR REGULATORY COMMisslON WASHINGTON, D. C. 20555 Docket No. P-STN-508 MAR 'l 31975 l

-l R. C. DeYoung, Assistant Director 1

for Light Water Reactors, Group 1 Division of Reactor Licensing RESAR, REVISION 3(RESAR-3)

In accordance with your request of March 5,1975 to identify unacceptable sections of RESAR-3, the Structural Engineering Branch has updated the review of Section 3.7 " Seismic Design" of RESAR-3, including the proposed Section 3.7 Amendment to the Consolidated Version of RESAR-3 dated September 30, 1974.

We had a meeting on July 19, 1974 with Westinghouse to discuss i

draft questions on Section 3.7.

Most of the questions of the draft list were later asked formally in a letter.

(Vassallo to Salvatori, August 8,1974). As a result of this me.eting, it was the staff's impression that Westinghouse would comply with each of the positions discussed except one on combination of modes with closely spaced frequencies.

In reviewing the proposed

' Section 3.7 Amendment of September 20, 1974, however, we find that a clear intent of compliance with our positions is lacking

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and a restatement of unresolved items is necessary.

Enclosed is a list of such outstanding issues.

o c. W R. R. Maccary, Assistant Director for Engineering Division of Technical Review

Enclosure:

List of Outstanding Issues cc w/o enc 1:

cc w/ enc 1:

A. Giambusso S. Hanauer L. C. Shao W. Mcdonald F. Schroeder C. P. Tan D. Vassallo D. C. Jeng M. Aycock S. P. Chan

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MAR 131375 LIST OF OUTSTANDING ISSUES OF RESAR-3 1.

Design criteria to account for relative displacements between component support points. (Formerly Question 3.13) 2.

Combining modal responses for modes having closely spaced frequencies to each other. (Formerly Question 3.16) 3.

Definition of "o to reflect the meaning of maximum response due to i-th direb[ ion input and a statement to indicate statistical independence of three directional inputs. (Formerly Question 3.18) 4.

Design criteria to account for relative displacements between piping support points. (Formerly Question 3.19) 5.

Pertinent data for concluding that the known variation in properties of component; and systems does not account for any measurable or significant shift in period or increase in seismic loads. (Formerly Question 3.20) 6.

Damping values for the control rod drive mechanisms and the fuel assemblies. (Formerly Question 3.22)

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n idAP 13 EiS i

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LIST OF OUTSTANDING ISSUES OF RESAR-3 4

.j 1.

Design criteria to account for relative displacements between component support points. (Formerly Question 3.13) i 2.

Combining modal responses for modes having closely spaced i

frequencies to each other. (Formerly Question 3.16) t 3.

Definition of "o

" to reflect the meaning of maximum response due to 1-th direbbion input and a statement to indicate 4

statistical independence of three directional inputs. (Formerly Question 3.18) 4 4.

Design criteria to account for relative displacements between piping support points. (Formerly Question 3.19) a

]

5.

Pertinent data for concluding that the known variation in properties of ccmponents and systems does not account for any measurable or significant shift in period or increase in seismic loads. (Formerly Question 3.20) 6.

Damping values for the control rod drive mechanisms and the fuel assemblies. (Formerly Question 3.22) 3.

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pq 131975 y

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- DOCKET NOS and.STN 5.07509 1

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/ '; APPLICANT: Washington Public' Power Supply System (WPPSS) '

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j?N.:PACILITTs f MPPSS.Muelear. Projects MoZ 3 and No/5YU9MM. ' ' Vf; f ',

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W' if A

%g8mOl&IT OF: PEREUART3SO19W3tBETING WITE VPPSS RECARDINC GROUNDWATER DRAINAGE V

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. Don Februaryi23 gl973,? representatives..of WPPSS and Ebasco met with the NRC '

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h60 staff in Bethesda.'Nr.WPPss had regoested the meeting in order to discuse. the ' M.

i roposed 'grounduist drain' age system,for WPPSS Nuclear Projects No. :3.and

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.No! 5.", A list.'of attendeis is attached.

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l Ebasco presented a brief description of the site area and the location of the two Category I buildings (one for each unit) at the site. In introductory I

remarks, Ebasco explained ;that the concept of the 8toundwater drainage I

system is to permanently'1'ower the groundwater level at the site with i

.sa. lospectable and voyairable gravity drainage system around each Category 1

I buildingf If the'syst'esishouldifail.Ebasco claimed that it will take

' M' 26[theVaroundwheElehel seek's long time to recover thdt the system can J

l 4bedrepaired before the groundwater level exceeds the design level.

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iTho 'p[erposes, ef. "the grovedwater ' drainage system are the following s -

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.1(1),.To prevent water from esep.ing through the foundation walls.

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1(2)' To relieve tho' walls of hy'drostatic loading.

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.(3) To improve ' stability conditiona under earthquake loading.

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To increa..'s4 sidi.fr.g. ion oe' the walls..

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.l JL 4 (6 foleliminateiontside forse en tho' walls.end water proofing.

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Ebasco then' described the groundwater' drainage system.

The system consists of i

verti' cal drains spaced at 8.5 ft. intervals around the Category I huildings.

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These vertical drains extend from plant grade to the base of the foundation mat. The drales coneeet. with an'8 in. horizontal header which collects the runoff. The runoff is then routed via manholes to a 6 ft. diameter decinage I

tunnel (common to both units of the facility) that drains into Workman Creek.

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. MAR 131975

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.s The.following inspection program for the groundwater drainage system was

c. y, described by Ebasco:

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., M /f' (1). Inspection 'of ' vertical drains -'s light will be shone _into the ddhhhh.,h. drains' to facilitate"visuallinspection.s;,yMS: 4 Mi;.,$.' j; 4

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-&&h2;&h?h d?fi.O'@%;L(2),f,p inspection-of;herisontal,heade & $ 5 1 W ' N 'O W N $ W ll 5O.4%YWWW* the headers - to facilitate visual inspection.J J,'

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C MM5}$jf(3)'M (-$ conducted to the,' concrete plug'in the; tunnel interior.

. Inspection of! drainage

• tu nel Ma usik-through the tunnel will be a.

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@V'27'.. light will be shone through' the plug to' facilitate visual' inspection j'j S

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- of the rest of'the tunnel..

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According to Ebasco, the drainage system can be repaired in the following l f, i

menner:

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. (1)L Vertical drains or horizontal headers - can be drilled out using I

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.s. power auger or opened with a high-pressure strea:s of water.

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...e' e s htM.2(2) iDrainage' tunnel.Fcan' be excavated by hand.T

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.Eb'aseo presersted the results of.scue preliminary calculations of the ef fec'ts -

c of the ggundwater drafrage system. Assuming a permeability for the rock of

- [0.5 x 10 cm/sec, a rainfall'of 10.in. per month and a rainfall percolation

.of 1-2/3 in, per month, the total flow rate from the system af ter four years

- of draining was calculated to be. 25 CPM.'

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-The :following preliminary assumptions for,' drain operation were used by Ebasco j

'in the design developwst:

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' 9 Y (1) The model was surrounded by level ground.

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ljg$q;.w,(3) 4 The annual. ralafall' was ' twice the actaal. site f rainf all..

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. - %(4) Am ;entremely high' percolation rate was assumed for impermeable rock.

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y-(b) Rorisontal header can store some water if the drainage tunnel

.becomes blocked.

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MAR 131975 1

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gbasco sta'ted that total ' failure of the drainage systers would result in the i

l groundwater level rising from'the bottom of the foundation mat to 20 ft.

l above the bottom of the mat.in a period ranging from one month to 3-1/2 years.

.- ?The one mouth estimate was talculated assuming a perneability of 0.5 x 106 yy

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, j cm/see and a ' rainfall" perco1~ation of I-2/3 in. ;per month. The 3-1/2 year v

jfestimate: wee calculatedjas'soning the same permeability but no rainfall

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, protected from the' following hasards:, ~

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mS[;,0. ogbuildings.'and 'will route.the water to f tbe site storm drains.

W;;.^N(alyplood from" heavy"relal

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the groun' ' alopes avsy from~ the Category I'

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-rain.weter.ent'ering thel ground will drain through the groundwater

, drainage system..

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., ( b) garthquakes the groundwater drainage system is not Category I..

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.j:;N (e) Tornado ~ the groundwater drainage system is entireiy below grade.

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~ Cooling water. pipe break inside a Category I building - the ground-M ', g

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water system is, isolated by the walls of the building.

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(b) Cooling water pipe break.outside the Category I building

-pipes i

- : are separated from drainage system by rock.. Resulting water will

drain to site stora drains.

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At our request, gbasco' described the tests performed to obtain the permeabilities

~

l used in the design analysis.. The question of whether the system should be I

classifiedasCategoryIwas[ discussed.

Assuming that the system is not s.

f.

>>: classified Category.l and failse the time required for ' repairs was then dis-w.y l. cussed. W &r f;t W % %O,< $.*x.: G 1.T A M co W.N e.A t i V J ',

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g, n-3 Je stated the following; comments !about. the proposed groundwater drainage systen:

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,, yi(1).J Ar,least"the' esslio&?fQ:fQ$ V,f, f;p :

.h; les ?ia the system'should be classified as ' Category I.

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> 2)^Peetulated failurefef' outlets should be addressed.

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i. ~ (3) Inspection procedures' should be clearly established.

Groundwater level outside building should be monitored during constrcction and also during the operating life of the plant.. With such a monitoring program,

- Edefinitive information about groundwater level characteristics will be available before the. operating Ileense stage.

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Adequate capacity'of the sy, stem should be assured by pumping test data. ~ I l

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J5) Timely, repair capability should be assured.- l This is related to (4) above! M.w m.,

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, '.WFFSS stated, that the details of the' groundwater drainage syst'em would

([MT

},,> be]sobeitted with< the, responses to the. staff's ~second ' round.of ' requests '.

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3 cc: Washington Public Power Supply System ATTN:

Mr. J. J. Stein Managing Director 3000 George Washington Way Richland, Washington 99352 Joseph B. Knotts, Jr., Esq.

Conner, Hadlock & Knotts 1747 Pennsylvania Avenue, N. W.

Washington, D. C.

20006 Richard Q. Quigley, Esq.

Washington Public Power Supply System 3000 George Washington Way Richland, Washington 99352 f

l 4

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e ENCLOSURE ATTENDANCE LIST FEBRUARY 25, 1975 MEETING WITH WPPSS

i

=-----

f 1

Nuclear _ Regulatory Commission Washington Public Power Supgly, System

' I P. O'Reilly D. B. Whitford I. Sihweil G. C. Sorensen C. Y. Liang l

L. G. Hulman D. L. Milliken J. T. Greeves Ebasco D. Jeng T. Johnson W.

D. Rezak R. J. Norman A. II.

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A. W. Barchas T. Raney f

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s Distribur*

Docket F' R. Tedesco NRC PDR V. Stello Iex:a1 PDR R. Maccary NRR Ramiing (M. Groff)

H. Denton R. DeYoung V. Benareya V. } bore C. Iaig D. Skovholt J. Kastner D. Muller G. Iainas R. Denise D. Ross K. Goller T. Ippolito G. Lear J. 1(night W. Butler S. Pawlicki J. Stolz L. Shao R. Clark B. Grimes i

T. Spies W. F,a =411 D. Vassallo R. Rallad K. Kniel P. Fine

0. Parr T. Novak A. Schwencer M. Spangler R. Schemel EP Project Ma v.

J. tbrris D. Ziemann Attomey, EID P. 6 11 ins IE (3)

R. Purple V. Wilson G. l<nighton ACRS (14)

G. Dicker Project Mana6er - P. 'O'Reilly B. J. Youngblood IWR l-3 Reading IWR 1-3 File W. H. Regan, Jr.

R. Vollmer L. G. Hulman W. Houstal D. L. Milliken

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S. Varga D. Jeng R. W. Klecker F. Kantor F. Schroeder V..Goel T. Johnson C. Stepp J. Greeves D. Budge T. Hirphy R. Kornasiewicz C. Liang P. Stoddart J. Costello F. Cherney P. Chen E. Brooks R. Satterfield G. Manz F. Ashe M. Bolotsky I. Sihwe11 L. Phillips R. Culp 6

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