ML18018A722

Forwards Request for Addl Info Re Hydrologic Engineering & QA List.Response Requested in Time to Support Nov 1983 Target Date for Issuance of SER

ML18018A722
Person / Time
Site:	Harris
Issue date:	08/17/1983
From:	Knighton G Office of Nuclear Reactor Regulation
To:	Utley E CAROLINA POWER & LIGHT CO.
References
NUDOCS 8308300831
Download: ML18018A722 (10)

Text

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AUG 1.7 1983 Docket Nos.:

~50-400 and 50-401 Mr. E. E. Utley Executive Vice President Carolina Power

5. Light Company Post Office Box 1551 Raleigh, Norgf Carolina 27602

Dear Hr. motley:

DISTRIBUTION I'ocument.Control NRC PDR L PDR NSIC PRC System LBk3 Reading JLee EALicitra

Attorney, OELD

Jordan, IE Taylor, IE ACRS (16)

TMNovak JSpraul RGanzales j

pP' 50-500/401 Subjects.

Request for Additional Information - Shearon Harris As a result of our continuing review of the Shearon Harris FSAR, the staff has identified. the, reed-for additional information in the areas of hydrologic engineering and the gA List (Table 3.2.1-1).

The specific information required is shown in Enclosure l.

We request that you submit a response to the enclosed request in a timely manner to support the target date of Navember 1983 for issuance of the SER.

With regard to the gA list in the enclosed

request, please note that Item 260.67 is a revised version of Item 260.67 which was previously trans-mitted to you.

The only changes to this item are the addition of subpart a.17 (valve operators for safety-related valves) and the deletion of subpart c.l (plant-safety-parameter display console).

The remaining subparts to 260.67.t have been renumbered accordingly.

Please advise us as to when you plan to respond to this request.

If you have any question regarding the request, you should contact the project manager.

Sincerely,

Enclosure:

As stated Original signed b'II George 5 iimghton George W. Knighton, Chief Licensing Branch No.

3 Division of Licensing cc:

See next page 8308300 pgpp0400 830817 pDR ADOCK pDR DL:LB83 EALicitra v

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OFFICE/

SURNAME/

DATE0 NRG FORM 318 (10-80) NRCM 0240 Gl Knighton

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8/ j(p/83

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OFFlCIAL RECORD COP.Y USG PO: 1981-3M-960

t a.,

fi.

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Shearon Harris Mr. E.

E. Utley Executive ~lice President Power Supply and Engineering and Construction Carolina Power 5 Light Company Post Office Box 1551

Raleigh, North Carolina 27602 cc:

George F. Trowbridge,

Esq, Shaw, Pittman, Potts 8

Trowbridge 1800 M

Street, NW Washington, D.

C.

20036 Richard E. Jones, Esq.

Associate General Consel Carolina Power 8 Light Company 411 Fayettevil1'e Street Mall Ral ei gh, North Car ol ina 27602 M. David Gordon, Esq.

Associ.ate Attorney General State of North Carolina Post Office Box 629

Raleigh, North Carolina 27602 Thomas S. Erwin, Esq.

115 W. Morgan Street Raleigh, North Carolina 27602 Mr. George Maxwell Resident Inspector/Harris NPS c/o U.S. Nuclear Regulatory Commission Route 1, Box 315B New Hill, North Carolina 27562 Charles D. Barham, Jr.,

Esq.

Vice Presi dent 5 Seni or Counsel Carolina Power 8 Light Company Post Office Box 1551

Raleigh, North Carolina 27602 Mr. John Runkle, Executive Coordinator Conservation Council of North Carolina 307 Granville Road Chapel Hill, North Carolina 27514 Mr. Wells Eddleman 718-A Iredell Street Durham, North Carolina 27705 Mr. George Jackson, Secretary Environmental Law Project School of Law, 064-A University of North Carolina Chapel Hill, North Carolina 27514 Dr. Ph(j)is Lotchin Chapel Hill, North Carolina-27514 Mr. Travis Payne, Esq.

723 W. Johnson Street Post Office Box 12643

Raleigh, North Carolina 27605 Mr. Daniel F.

Read, President CHANGE Post Office Box 524 Chapel Hill, North Carolina 27514 Bradley W. Jones, Esq.

U.S. Nuclear Regulatory Commission Region II 101 Marietta Street Atlanta, Georgia 30303 Richard D. WHson, M. D, 725 Hunter Street Apex, North Carolina 27502 Regional Adminstrator - Region II U.S. Nuclear Regulatory Commission 101 Marietta Street Suite 3100 Atlanta, Georgia 30303 Karen E. Long, Esq.

Staff Attorney Public Staff NCUC Post Office Box 991

Raleigh, North Carolina 27602

Shearon Harris Dr. Linda Little Governor.'s Waste Management Board 513 Albemarle Building 325 North Salisbury Street

Raleigh, North Carolina 27611

HYDROLOGIC ENGINEERING SAFETY QUESTIONS SHEARON HARRIS NUCLEAR POMER PLANT UNITS l AND 2 DOCKET NOS.

50-400/401 240.19 In Section 2.4.1.1 of the FSAR you stated that, should the flow (SRP 2.4.2) through the drainage system for the plant island area become blocked during a Probable t1aximum Precipitation (PHP) event, the plant island is capable of being drained by overland flow on the open roads and on the ground surface.

This issue was left as an open item in the draft'ER pending your submittal 'of a site grading plan.

Subsequently, you provided the staff with drawings of the site grading plan for their review.

The staff has reviewed the site grading plan and concludes that, if the drainage system were to become blocked, water resulting from a PMP event would not be sufficiently drained away by over-land flow.

This is because the plant site roads, which are raised about a foot above plant grade to elevation 261 feet, will cause water to pond higher than exterior door entrances which are also at an elevation of 261 feet.

You should therefore determine the maximum elevation to which water will pond during a PHP event assuming that all drains are

blocked, and describe all safety related structures that will be affected by this ponded water.

In addition, you should address the impact of this water on the plant's ability to be safety shut-down if"'necessary.

You have not provided any information regarding the elevation of the plant railroad tracks.

Are these tracks elevated above plant grade?

If they are, you should also consider any ponding which could be caused by the elevated tracks.

As an alternative, you may want to lower the plant site roads and/or railroad tracks in certain areas to prevent water from ponding above an elevation of 261 feet.

If you select this alternative, you should provide drawings showing areas where roads will be modi-fied together with the design bases used to determine the length of road and/or tracks that have to be lower ed to prevent excessive ponding.

You may also want to consider other engineered features to pre-clude flooding of safety-related structures.

Examples of engi-neered features that have previously been found acceptable to the staff include:

a)

Artifical barriers such as water tight doors and b)

Low structural barriers such as curbs located inside or out-side safety-related buildings.

In determining the magnitude and temporal distribution of PMP, you used Hydrometeorological Report No.

33, "Seasonal Variation of the Probable maximum Precipitation East of the 105th Meridian for Areas of 10 to 100 Square Miles and Durations of 6, 12,24 and 48 Hours"; and "Design of Small Dams",

U.S.

Department of the In-terior, respectively.

The National Weather Service has recently published two new reports that should be used to determine PMP values and distribution.

The first of these reports is Hydro-meteorological Report No. 51, "Probable Maximum Precipitation Estimates, United States East of the 105th Meridian", June 1978.

The second report is Hydrometeorologic Report No. 52, "Application of Probable Maximum Precipitation Estimates - United States East of the 105th Meridian", August 1982.

Both of these reports should be used in your reevalution of site drainage

'250.20 The site drainage drawings that you provided show inner and outer (SRP 2.4.2) security fences surrounding the plant.

In the past, the staff has found cases where security fences are located on elevated earth or gravel berms which obstruct the flow of water.

Are the

, security fences at Shearon Harris located on elevated berms which could cause additional ponding?

Please provide a drawing showing details of the bases of the security fences.

Harris.,

Request for Additional In ormation 250.0 260. 67 l}uality Assurance Branch Seciion 17.1.2.2 of the standard ormat (Regulatory Guide 1.70) requires the identification of safety-related structures,

systems, and components controlled by the gA prooram.

You are requested to supplement and clarify the Harris FSAR in accordance with the fol lowing:

a.

The following items do no appear on FSAR Table 3.2.1-1.

Add the appropriate items to the table or justify not doing so.

2.

Containment em rcency sur.;ps Equipment hatch and personnel air locks 3.'.Guard pipes and leak-tioht. compartmenis for containment

. em roency sump recirculation lines and valves Engineered sa ety features ac uation system 5.

Charcoal filters in the control room HYAC system 6 ~

Fuel bui 1 di no radiation moni tor,

.7.

Roof and site drainaoe sys.em includino drains,

parapets, or a di no,.cul ve r is, a nd cha nne 1 s AC Onsite-Power Sysiems (Class 1E)

Diesel oenerator

governor, voltage regulator, ano exci ta 71 on system Insirumentation,

control, and power cable splices, connec ors, and ter;,final blocks Conouit and cable tl ays ano the'l1 suppo Ts which do no. contain Class 1i cables but whose

=a ilure may damaoe othe) 'safety-elated items Load'eouencer AC control power inveriers AC viital bus cistribuiion equipment DC Power Systems (Class 1E)

ei

~ i NUREG-p737 (Enc)osure 2)

Clarification Item:

reactor coolant system YP-;its

!i.B-l r 1 art sni ell dine

."-os-'occi cen='a-.p) ing ccpabi I i i. ies Ii P 2

ii P 3

)'c, IV P

S i;ion ir>0 i Ca ion.

I I. D. 3 5.

nu il 1 el y feecNB >.er Syst6n

~ 8 6

~ "iliary >eec'~ater syst.a II. E. i. 2 7..

~->er-"ency po~er i or pressur.i:er

'A~a-'e r.S II. c. ~.1 8.

DeC i C

. ed i~>YQrOCen penetra

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b I'ock va1 v s )

a>.

I evel in'>cators

~ui.oi ia 'lc PGPiV 'Iso) a i.ion II. K... 1 13.

I-!0 con-.ro1 Ier 1) 8 Q

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14.

J-.n '.c'",:-tory r:-ctor tri: on>

-'Urbin trip

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15.

Fo~er c; pu-e,p Sea IS I!.K. 3. 25

) 6 Eeii" i cency 17

~et oeACY pl ans sL ="Dort =a c111 i i es

. '/ >!!.4.2 I I I. A. l. 2 I I I. D. 3. 3 I>i.D..3 L

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Conduit and cable trays and iheir supports which do not contain Class 1E'cables but whose failure may damage other saiety-related items B~ttery racks Protective relays and coritrol panels II 10.

Radioactivity sampling (air, surfaces, liquids) 12.

Radi oacti vity contami ncti on m= asurem nt and ana lysi s equi pment Personnel monitoring eouipr:. nt (iniellial, e.g.,

whole body) 13.

Instrument storaoe, cal ibration.,

and miaintenance prooram 13.

Decontamination aciliiii s, personnel, anG eouipment Respiratory protection eouipmeni (including testino)

'6.

Contamincti on control'7, Valve operators for saiety-related valves.

b.

Clariiy Table 3.2.1-1 as noted below or justify not ~oino so.

r Provide a.conmitment that cll safety-re'.ated instrumentation and controls (IEC) described ir, FSAR Section 7.i throuoh 1.6

. and other saiety-relate.

IKC =or safety-relcteG fluid systems will be subject to the "=rtinent requirem.nts of the FSAR Appendix 8 gA program.

This can be done by a iootnote to FSAR Table 3.2.1-i.

Under "Electriccl Sysie)

~.- and Co-..pcnents" cn FSAR Amendmert 3 paoe 3,2.1-43. is Saf.-'.y-relatec powel" CGr)il 01 and instrument cables and raceways..

It cppears tha:

a commie should be inserted after "power" and one after "control."

t')Gies 26 and 27 to FSAR;ab le 3.2. 1-sta qui red informict 1 on ccn be founc In Tcb l e 1'.4.2-1 does not have this in)or))ation, is needed.

ie -.hiai some re-i1. 4. 2-i.

Table and clarifica;ion C.

FSAR Amenoment 3,

on paoe 3.2.1-42, incluce's "Post Accident t';or)itoring Instrumentation lii.'REC 0737."

However, Enclosure 2

ofi HUREC-0737 identiiied nunero))s othel ite".5 tha a

e clso safety-related or of such im-Grtance to safeiy tha ~ they should have the'ertinen).

requirements c= the FSAR Opera" iional gA program applied.

These iters are listeo below.

Provice such comm)itment in Table 3.2. i-i oi the FSAR ol justify not doing so.

I