ML20210T263

Forwards Industrial Security & Emergency Planning Branch Requests for Addl Info Re PSAR Chapters 13.3 & 13.7

ML20210T263
Person / Time
Site:	Satsop
Issue date:	09/24/1974
From:	Skovholt D US ATOMIC ENERGY COMMISSION (AEC)
To:	Deyoung R US ATOMIC ENERGY COMMISSION (AEC)
References
CON-WNP-1341 NUDOCS 8605300005
Download: ML20210T263 (10)

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trench & LPN Requesting Assistance: LIR 1-1, P. D. O'Reilly Review trench Involved: L:IS&EP Roguested Completion Date: 9/27/74

,S aaview Status: 01 complete j

'he attached report contains informaties requests relative to our reviw of the subject SAR for transmittal to.the applicant in accordance with the review schedule.

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rn u.si;te.is umc'i ir.tleces inforr::aticq c. ai fir.dino". which, l il M

r. 'ded to cssore r..cuary cf carge: cy eitnning '.'iih rcspecT. ic

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(1) Picts shouin, projected dose levels for both whole body ar.d thyroid, resultiro fren the r:ost serious deri,a basis eccident analyzed in the Scf ety In'.ilysi?

Peport. These should t,e basei ui:en the sere isotocic 4

realar.se rites tc the etrosrl.ere, tre sar..e disnersion tactel, and tat, ca.ne rat'oro' 001, es ::re postacted for the L os t con'; r'.wi re ca t c i t: Ci. apter 15 ef the FSM for

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Include sufficient inferratica to support. your citirte.

(3) /.n esti-ste of the tira cccuired to notify tb pc;.ulation-at-r:sk and the r.ecns assur.ad for ruch esticate.

(/. ) An estiT-te of the evacuation tires to re: ove corscrE tram the cyclusion crca, and from ccch " sector", or ir. crc"?nts ther>c. cT ths cr,virens out to a distcnre deterzined by r

the 3 ocur terminus of thc 5 ren t; hole 50 :y dose curv:, the 25 re ; th roid curic, or the outer LPZ boundary. t hich ver

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is the createst.

From a oractical viewooint, the "stctors" chosen for anclysis may be bounded by certain ce:grcchical or r.an-made features, but should cover an arc of at least o

45, Population data should include both resident and transient perscns, including those resulting f rcr.1 thc facilitics described in Chapter 2 of the PSP., tt levels pro.icc.ted as peah values during the expected life of the plant.

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f or th" Cre? irs;in. Of CG9f t'ir : t0'l GP F90ncy r%!:-"i d plaDS for t'iC tn'!irCb5 Of tisi plant.

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fEP 1 y;4 Docket Nos. 50-508/509 R. C. DeYoung, Assistant Director for LWR-1, L RESPONSE TO STANDARD REVIEW ASSIGNFINT, WPPSS NUCLEAR PROJECT NOS. 3 & 5. REVIEW 0F PSAR CHAPTERS 13.3 AND 13.7 Applicant: Washington Public Power Supply System Licensing Stage: CP Branch & LP!! Requesting Assistance: LWR l-3, P. D. O'Reilly Review Branch Involved: L:IS&EP Requested Completion Date: 9/27/74 Review Status: Q1 complete The attacited report contains information requests relative to our review of the subject SAR for transmittal to the applicant in accordance with the review schedule.

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Donald J. Skovholt Assistant Director for Quality Assurance and Operations directorate of Licensing

Enclosure:

Information P.cquests CC; S. Hanauer A. Giambusso W. Mcdonald R. Houston O. Parr F. D. O'Reilly R. F. Priebe l

DISTRIBUTION:

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4 420-1 420.0~

I!!DUSTRIAL SECURITY aid EMERGE!1CY PLA!!!!!iiG BRAi;CH 421.1

. It is not clear that your employee screening progran conforms (13.7.1) to the requirenents set forth in AilSI fil8.17-1973, Section 4.3.

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Please indicate that your progran incorporates an investigation to disclose adverse character traits and an exanination by a licensed psychiatrist or physician to determine emotional stability.

If an alternate approach is used, indicate the screening methods utilized to obtain an equivalent effectiveness in achieving the aforenentioned objectives.

421.2 In order to evaluate the acceptability of the facility design uith (13.7) respect to protection agair.st industrial sabotage, the follouing additional inforration is required to deternine confornance witn the design recuirements set forth in T$equlatory Guide 1.17 and AllSI :118.17-1973. Your resunnse should be withheld fro 1 public disclosure pursuant to 10 CFR 2.,7M.

(1) Provide figures and/or drawings which identify the followina:

(a) Owner-controlled area, includinn private nronerty M rters, n rkinq lot (s). tM roads to be used for surveillance.

(b) Protectedarea(s),includingtheassociated isolation zone (clear area), physical barriers, access control points, lig;1 ting, intrusion monitoring and/or perireter alarn systens, and roads er pathways to be used for surveillance.

(c) Vital area (s), including all access points.

(d) Alarn statien locations.

(2) Provide sufficient information wi.ich sMus t:iat the physical barrier construction for the protected and vital areas satisfies the requirements set forth in AflSI fil8.17-1973, Sections 3.3 and 3.4.

(3) Describe the design features to be used for protecting all potential access points into the vital area (s) against unauthorized intrusion. Such features should include locking devices and intrusion detection devices.

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420-2 (4) Indicate that all intrusion alarms, emergency exit alarns, alarm systems., and line supervisory systems will meet the level of performance and reliability indicated by the Interim Federal Specification W-A-00450B (GSA-FSS), dated February 16, 1973.

(5) Describe the physical security protection to be utilized in the design for the protection of security system service panels and wiring for protective devices, security comunications systems, and door lock actuators.

-(6) Describe nessures taken, or to be taken, in the design or arrange :ent of ecuip"ent, other than casures for the control of access or detection of unauthorized entry, for rrotacti:1 of vital g uirrant a13 inst acts of Salatv,2.

(7) Designate the person or c'oup with the responsibility to conceive and detail security provisions in the physical plant desic.n. If this responsibility is outside of tha o..ner organizaticn, also soccify the position uitSir, your organization responsible for the eve ta' r is r v iv.7 nd twrol of "'r contractnd activities.

422 l 10 CFR Part 50, /;,;'endix E, requires that the Preliminary Safet'.-

(13.3)-

Analysis Report contain sufficient inferration to assure tua co-'patibility of proposed energency plans with facility desicn fettures, site layout, and site location with respect to such considerations as access routes, surrounding population distri-butions, and land use. To this end, we request that you su hit an analysis which includes information and findinas which will ::e needed to assure adequacy of cecrgency planning with respect to the protectiv: reasure of evacuation of persens fro 7 the exci area and from any potentially affected sector of the environ:, '

follous:

(1) Plots showing projected dose levels for both whole body and thyroid, resulting from the most serious design basis accident analyzed in the Safety Analysis Report. These should be based upon the same isotopic realease rates to the atmosphere, the sane dispersion model, and the same meteorology as are postulated for the most conservative case in Chapter 15 of the PSAR for purposes of showing conformance to the siting dose criteria of 10 CFR Part 100. Plume front transit tines, radioactive decay in transit, and dose conversion cal-culations may be incorporated on a physically realistic basis or conservatively simplified basis.

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b 420-3 Present the data in the following format:

(a) Use a 109-109 scale with time (hour) following onset of release as the ordinate, and distance (miles) from the release point as the abscissa.

(b) Provide curves for whole body doses of 1, 5, and 25 rem, and thyroid doses of 5, 25, and 300 rem. Each curve should represent the elapsed time to reach the specified dose level as a function of distance from the release point.

(c) Each curve should extend to a time of 8.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, and from a distance equal to the exclusion radius or fron 2.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, which-ever represents the lesser distance for each curve.

(2) The expected accident assessment time which includes the time required to identify and characterize the accident, the time required to predict the projected doses resultinq from tSe accident, and the tire requircd to deterN ne the appropriate protective measures for tne atrectec orcas, include suf ficient inforration to support your estirate.

(3) An esticate of the time required to notify the population-at-risk and the reans assunad for such estir. ate.

(4) An estimate of the evacuation tires to rerove persons from the exclusion area, and fron each " sector", or ircremnts thereof, of the environs out to a distance determined by the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> terminus of the 5 ren whole body dose curve, the 25 re-thyroid curve, or the outer LPZ boundarv. t:SicMv?r is the greatest. From a practical vienoint the ' scc *ces' chosen for analysis ray be bounded by certain ceegraphical or man-made features, but should cover an arc ~ot at icast o

45. Population data should include both resident and transient persons, including those resulting from the facilities described in Chapter 2 of the PSAR, at levels projected as peak values during the expected life of the plant.

(5) The identity and character of egress routes and the means assumed for effecting the physical evacuation.

p 420-4 422.2 The information submitted in Section 13.3 of the PSAR is (13.3) deficient with r'espect to the requirements of 10 CFR Appendix E, paragraph II. Provide the following:

(1) Identify the principal agency in the State of Washinoton which has been designated to have the overall 'respon-sibility for radiological energency planning.

Indicate the arrangements that have been made with this agency for the preparation of coordinated emergency response plans for the environs of the plant.

(2) Describe the features of the facility'to be provided for onsite emergency first aid and decontamination.

(3) Describe uhat arrange ~ents will be cade to ensure -

energency transportation of individuals to offsite treatment facilities.

(4) Identify at least two hospital facilities and provide evidence that prelininary contacts have established agreements and potential capability to receive and treat individuals af fected by radiological emergencies.

(5) Descriue tae features of the facility to tY urovided to assure the capability for plant evacuation and the caratility fcr facility reentry folicwing evacu3 tion in order to nitigate the consequences of an accident.

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